ML20236T614

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Rev 0 to Special Test Instruction STI-33, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage
ML20236T614
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 08/17/1987
From: Kephart J
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20236S034 List:
References
STI-33, STI-33-R, STI-33-R00, NUDOCS 8712010400
Download: ML20236T614 (239)


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I am familiar with requirements the activity of being to be performed t.nd understand the Test Director.

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Signdt'ure

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Dhte' sf, Other Test Directors assigned by the Responsible Supervisor are listed below

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- CONTROL C00M CONTDOL L ED COPf ES INSTRUCTION WORK PACrAGE l

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SQA119 Revision 7 ATTACHMENT 1 SCREE

  • JING REVIEW TORM ,

FOR DOCUMENTf MG APPt ICABitITY OF 0500 EVALUAf f 0N P

AN INSTRUCTIO

N. PROCEDURE

, RA0 TEST WASTE OR SYSTEM {

L EXPERIMENT SHEEYS PROPOSED NAY DE ATTACHED AS NECESSARY.TO BE CONSIDERED .

ADDITIONALAT SQN NUCLEAR F PRECAUTION: *

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USE ATTACHMENT 3 MJ.N PERFORMING THE SCREENING REV .

I DOCUMENT NO. AND REVISION: O f DESCRIBE CHANGE AR'M Rra P'sE1= O -- m I ""*b n#,/? 4 Frf FLWcrtnolr1Li n n fe t ~

I k AWD ST7-94 cihwrnrnrr (ctn inerJPFA'Af rn onifMw'( -- n F FF TYPE OF ACTIVITY (Chance. Tast. .

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3 OPERATING YES V NO CHARACTERISTICS) FROM THA

,. IF YES. A USQD EVALUATION IS JEQUIRED.

FSAR SECTION RESEARCHED _ (s N ,10 4 a'7. 2 a 9 '?. d , 9. El 2.

DOES THE PROPOSED CHANGE INVOLVE NEW . OR PROCEDURES OR

REVISIONS PROCEDURES YES V _NO TO INSTRUCTIONS AS OfSCRIBED IN THE FSAR OR PLANT TECH OR PROCEDURES. THAT SPEC A' IF YES, FSAR SECTIONARESEARCHED USQD EVALUATION l%. .I - IS RE VIRED. O 6 O -

1 sk+! ~ 4 *b b

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f AMENOMENT IF YES

_YES _ NO " ISSUED BY THE NRC TO AUTH td/A

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If t40, a USQD is required.AT 'I - M klO -

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f FSAR SECTION RESEARCHC0 l l . 2- . 'A.

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5.

CONDUCTED SPECIFICATIONS? V YES OR IMPLEMENTED WliHOUT A CHANGE TO T NO IF NO, RETURN THE DOCUMENT TO THE ORIGINATOR FOR REVISION MODIFICATION, OR INITIATION OF A TECHNICAL SPECIFICAi!ON CHANCE .

I TECH SPEC SECTIONS RESEARCH 4_ '

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  • PREPARER: ___j c A i

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ADDIT!0NAL JUSTIFICAT!0tu!NFORMATION IS REQUIRED NO IF YES, LIST APPROPRIATE REFERENCE DOCUMENTS. _YES

,(- APPROVED DY: -

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< STI-33 Page 7 Revision 0 4.0 PRECAUTIONS AND LIMITATIONS

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4.1 The area around the exposed ends of the cables under test must be roped off or isolated by means of orange tape and caution signs.

4.2 .

, Only authorized testing and support personnel shall be allowed

< within the roped off test boundaries while the test is in progress.

4, 4.3 Personnel shall.be stationed in the area of the exposed ends of s[$

L g "

the test cable while the test is in progress, to preclude any ot entry into the test boundary.

[,J,2 h' k, '

4.4 r 'h Cable testing must be scheduled and coordinated so that at no time

, '[d ) [ g will both trains of safety related equipment (Train A and Train B) be placed in an inoperable condition.

g4 74 The redundant train shall be verified operable prior to removing equipment from service, I1 o +h5 s' ?i 4.5 Any deficiencies found during the conduct of this. test shall be I documented on the test Deficiency Log, page 15 of the Data Package.

f($ 0 E 2gyi4.6 Test equipment used in the conduct of this test shall be j4 ]$,n ys4 documented on the Special Test Equipment Log, page 14 of the Data Package.

, k h, 4.7 When working near energized electrical equipment, use extreme 4ot

4, , caution from to minimize the possibility of electrical shock or burn occurring.
  • 5

)v[Nk 4.8 Temporary measures will be used within this instruction to

,4 a

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' minimize and contain water leakage as applicable. Should inadvertent water leakage occur, the Test Director shall

's 4 gg immediately initiate steps to secure high potential testing, 2 9 n. y 9 contain the leakage, notify the SE as required by site procedures.

  • Ts and initiate work requests as required for cleanup activities.

d1, **3-$ Q' g g' 4.9 Common Mode Failure - Redundant Measuring and Test Equipment bkD'. M (M&TE) may be used after calibr'ation is verified (it shall be assumed that the M&TE was used for Train A prior to this test).

"' Reference SQM1 and AI-31.

+

4.10 Testing of the first cable to be tested shall commence within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of completion of the water injection per source document 2.1.2, enclosure 2.

'/4U 1 So the equipment in this STI are the same as those4h '

STI-34. In o STI, STI-33 and STI-34 muse able to perform functional' tests in this completed ind jepen4-(P Ta T ,o.the r- ,rmed'and functional test perf Qrmed arRFcompleted before STI-34 orere viseoie 3II-33 Med) be versa. -

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INSTRUCTION NO. # 7'I U A O Asn w A #alv/q r LATEST REV. DATE 8//5Y6'7 PAGES AFFECTED r DESCRIPTION Or CHANGE (AITACH U500 AND REVISED e .- 4 A.rs/PAGES) AMe n',,

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. =. .

/ f/2Nd,7 Approwea dy Ohte SHOULD THIS REVISION AND PERf0RMANCE OSERVE YES M NOAS 2YR REv!EW?

[F YES , ATTACH A COMPLETED SI-I APPENDIX -

JDIX E

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  • IMPLEMENTED AffECTS /

ASME COMPONENTS / CRITERIA)

PORC REVIEW DAIL.

Allf2 0 01007

' ' " '- ' ' W 4 PLANT MANAGER (OR DES!GNEE) APPROVAL C  !. f DATE APPROVED __

CHANGE MAY Now BE IMPLEMENTED

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0 PIES Of FORM DISTRieurED A5 fotLOW5: __.

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j ATTACHMENT 1 I

(CRErNING REVIEV FORM

~ FOR DOCUMENTING APPLICABILITY OF USOD rg'tA_gqq AN INSTRUCTION. PROCEDURE.

CONSIDERED AT SQN RADWASTE NUCLEAR FACILITY. S EXPERIMENT PROPOSED TO BE SHEETS HAY BE ATTACHED AS NECESSARY. ADDITIONAL PRECAUTION:

USE ATTACHMENT 3 WHEN PERFORHING Tine SCREENING REVIEW. *

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DOCUMENT NO. AND REVISION: Y"7'I ~ 3 3 IO DESCRIBE CHANGE _ A/./ -44Le

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ca., /l~ d n.M ./,_ / m /, .;.oef s:. _ ne ~,.,,

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-/ y TYPE OF ACTIVITY (Chanoe. Test. or Exoeriment)

1. .

OPERATING YES d _ NO CHARACTERISTICS) FROM THAT DE IF YES, A USQD EVALUATION IS REQUIRED.

FSAR SECTION RESEARCHED 9. 3 . */ 't S'

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2.

DOES THETOPROPOSED REVISIONS INSTRUCTIONS CHANGE INVOLVE THAT OR PROCEDURES, NEW ARE PROCEDURES DIFFERENT FROM OR INSTRU THE PROCEDURES YES _v AS DjSCRIBED IN THE FSAR OR PLANT TECH SPECS?

NO IF YES, A USQD EVALUATION IJ REQUIRED. -

FSAR SECTION RESEARCHED _ 7. 's % 1 -f

+ 3.

IS THE PROPOSED TEST OR EXPERIMENT DESCRIBED IN THE FSA ANENDMENT ISS YES BY THE NRC TO AUTHORIZE THE TEST OR EQUIPMENT?

_ _ NO IF YES, PROVIDE A REFERENCE TO THE FSAR SECTION OR LICENSE AMENDHENT.

If NO. a USQD is required. ~

4

- WHERE /THE YES NO RADWASTE SYSTEH IS NOT DESCRIBED IF YES. A USQD EVALUATION IS REQUIRED.

FSAR SECTION RESEARCHED //. #

S.

CONDUCTED SPECIFICATIONS? V OR. IMPLEMENTED YES NO WITHOUT A CHANGE

, IF NO, RETURN THE DOCUMENT TO THE ORIGFNATOR FOR REVISION, MODIFICATION, OR INITIATION OF A TECHNICAL SPECIFICATION CHANCE .

TECH SPEC SECTIONS RESEARCH ~3 N a /. L

^ S$ s e l

PREPARER: /

Date _ E 4*7 ADDITIONAL JUSTIFICATION /Inr0RMATION IS REQUIRED _ YES /

IF YES, LIST APPROPRIATE REFERENCE DOCUMENIS. _ NO /

APPROVED BY:

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.Page 13 SQA119 Revision 7 Standard Practice "

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ATTACHMENT 2 Unreviewed Safety Question Determination (Safety Evaluation) -

Use Additional Sheets As Necessary A.

Description of Proposed Activity _ ed/ ca44. /vuvo4 k SI-23 0 -

B.

Systems, structures or components affected c/

,sk va A- /- sev.h ; 9 9

~ J i k n ,,. , , m , b A, o, n ~ ~ .1 cl/&

f C.

Safety functions of systems affected A - 1 A p M ee .,1~ yL lf  % ., , - /Z.s ~er-c,/ &

~ ,} ra L~ - cLuJ,6cL y - D ~. A,4 ,

D. Effects ca safety .6 a-/4 d/

E.

Answer the following questions based on the evaluation documented in the preceding sections. Ensure that the basis for each of the -

following questions is addressed in the evaluation of effects on safety.

1.

Would the proposed activity increase the probability of an accident previously evaluated in the SAR? yes no /

{ 2.

Would the proposed activity increase the consequences of an l ,

accident previously evaluated in the SAR? yes  !

no _ t/

3. {

Would the proposed activity increase the probability of a malfunction of equipment important to safety? yes no t/

, 4.

Would the proposed activity increase the consequences of a

.. malfunction of equipment important to safety? yes_ no . t/'

.1

.* 5.

Would the proposed activity create a, possibility for an accident

_ ' of a different type than any evaluated previously in the SAR?

yes no /

16.

Would the proposed activity create a possibility for a malfunction of theequipment SAR? yes of a differen). type than any evaluated previously in no V 7.

~

Would the proposed activity reduce any margin of safety as defined in the basis for any technical specification? yes _ .

no 1/

l' f.

Does an unreviewed safety question exist?

1s approval no basis provided in D. O yes requires NRC

'l 8 7X+ > s e. & /n /,uj87 ACE g

(Preparer) Sigria ture/Da te/Sec t ion \

AUG 221987 PORC Review Date N. Yedbo AUG 221987 Plant Manager /Date 03175/vm

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.S77 - 3 3 A O e

- USQD-Page V of '1.1 ZCf 27-/r/8Y ATTACHMENT 2 USQD D. Implementation of I CF 97 + /#/6/

consequences of an accident previously evaluated in the FSAR, norwi will it increase the probability or consequences of a malfunction of equipment important to safety for the following reasons:

f, / %.s e fly , p - .r.e is r< - d fes ,.

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$4 fte s .Y c.fs.ht.a!, $a. at

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Ay , , /y -/sse a me fod. 4 /se, -t i=. v.*/~ J// e ot i , 4. ifx +s./p. .ri/< - :- .4 , f 4. -/:..,e./ o a / M *d "i..g ,:. /4 c.AJ .,cw 2.

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The test will be performed in accordance with ST1-33 RO, vid I6, a-.</

applicable procedures, ensuring that the test cables and conduc-tors disconnected, tested, and restored as well as other cables and conductors disconnected and restored do not affect equipment or components whose failure or actuation may increase the probabi-lity or consequences important to safety. of an accident or malfunction of equipment 3.

Plant design and construction assures adequate isolation between the test cables and other cables. Cable conductors of cables other than V4u I-uA J /* W have been determined to be less suspect of pullby damage. Also, all conduits and cable trays are grounded in accordance with TVA General Construction Specification G-40, " Installing Electrical Conduit Systems and Conduit Boxes." Therefore, if the test cable fails at a loca-tion outside of conduit MC14938, the shortest path to ground will be through another conduit or cable tray. ,

Implementation ofVlh Id /

does not create a possibility for nn accident of a different type than any evaluated previously in the SAR. The test does not af fect the plant configuration permanently, and plant configura-tion will other be restored applicable and documented in accordance with STI-33 R0 and arocedures.

There is no possi1111ty that malfunction of equipment of a different type than any eve.luated previously in the SAR will be created as a result of this test. Upon implementation and completion of Sfl-33 R0, plant configuration will be restored, proven functional as de signed, '

and documented in accordance with ST1-33 R0 and other applicaale procedures.. .

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USQD STI-33 R0 JdF 8 M Page + o f 5 ~'

.e f,.ft ADDITIONAL INFORMATION TO SUBSTANTIATE 0500

~

_ l.

TVA guides, standards, procedures and practices for installing class 1E cables were reviewed for evaluation by Franklin Research Center consul-tants to the United States Nuclear Regulatory Commission (HRC). The evaluation discusses significant dif ferences between accepted industry

  • practices and those employed by TVA at Sequoyah Nuclear Plant. Evalua-tion indicated that damage to cables could have occurred from pullbys, severe bending, jamming, and tension through 90 degree condulets.

Long-term random and accident-related common mode failures of cables are possible.

In order to assess whether significant damage has occurred, NRC of thehas recommended plant. tha.t cable tests be conducted prior to the startup TVA is, therefore, obligated to test worst-case repre-sentativeduring damaged lE cables to demonstrate to NRC that the cables were not installation.

2.

TVA electrical specialists and Mr. Reinhold Luther, a consultant on

" Generating Stations Cables" carried out investigations simultaneously on "In-situ DC Testing of Low-voltage Power and Control Cables."

Recommendations were to utilize a 240 volt per mil of nominal insula-tion thickness for t ting of low-voltage contr?. and power cables, as stipulated by IEEE S dard 383-1974. Subsequer :. view of test voltages was perform above recommendations. by a TVA cable task force, which revised the are to be applied to the Reference cables. 13 provides the test voltages that  :

3. i Although the dielectric strength of polyethylene and polyvinylchloride is 500 and 600 volts per mil, it was ennsidered that using the formula given in W. S. Raughley's memorandum to J. B. Hosmer dated July for calculating cable test voltages would be adequate to ensure no21, 1937 degradation of the cable insulation has taken place.

a thefault plantresulting from a cable failure during testingTransients instrumentation.

due to will not affect The grounding system at SQNP is designed to sustain transients due to faults at much higher voltages.

  • 4.

Criteria for cable selection, testing, inspection, and acceptance of cable pullbys, jamming, and cables supported by 90 degree condulets are provided in attachments 1, 2 and 3 respectively, in Mr. D.

and 8).W. Wilson's memorandums to Mr. M. R. Harding (references 4 5.

The following references are the basis for the Division of Nuclear ~

Engineering's decision to conduct the cable insulation tests. The -

tests provide evaluations, industry practice, recommendations and test criteria, as well as memorandums between TVA and NRC in ~

support of the proposed cable testing program. j 6

The DC high voltage test was specifically selected since industry experience has shown that it will not degrade sound cable insula-tion.

It will, however, identify any damaged cables and therefore confirm the integrity of those cables which pass the tests.

References of page SQEP-EEB, 0054E t  ;

U500 ST1-33 R0 .tdCf7/f8' Page -fr of & W REFERENCES

-p e{vn./V

.... 1.

Memorandum f rom Mr. T. W. Alexion of NRC dated February 20,1987, to Mr. B. J. Youngblood of NRC.

2.

ij. S. NRC - Letter from Mr. B. J. Youngblood to Mr. S. A. White dated March 9,1987, and Technical Evaluation Report by Franklin Research Center, dated February 19, 1987. ~

3.

Report.18,1987.

March f rom R. Luther, P.E. , (Consultant) for Mr. W. S. Raughley dated 4.

, Test Criteria - Memorandum f rom Mr. D. W. Wilson to Mr. M. R. Harding dated March 24, 1987. -(RIMS No. 825 870325 005) 5.

Memorandum from Mr. W. S. Raughley to Mr. D. W. Wilson dated June 12,1987.

(RIMS No. B43 870612 907) Superceded by reference 12.

6.

Letter from Mr. R. Gridley of NRC re. Cable Test Program.

7.

Excerpts from Stancard Handbook for Electrical Engineers - Tenth Edition - 1969.

8.

Memorandum March 30,1987. f rom Mr. D. W. Wilson to Mr. M. R. Harding dated (RIMS No. 825 870330 009).

9.

National Electric Code -1987 Article 351.

10.

Memorandum from Mr. W. 5. Raughley to Mr. J. B. Hosmer dated June 17, 1987 (RIMS No. B43 870617 904) Superceded by reference 12.

11.

Letter f rom R. L. Gridley to USNRC dated April 8,1987, "Sequoyah Nuclear Plant (SON) - Cable Test' Program" (RIMS No. L44 870408 802) 12.

LetterJune dated f rom W. S. Raughley (TVA to J. B. Hosmer (TVA) B43 870626 905, 26,1987, "Sequoyah Nuclear Plant (SQN) - Units 1 and 2- ,

Revised Cable Test Parameters" 13.

Reply July dated memorandum from W. S. Raughley (TVA) to J. B. Hosmer (TVA),

21, 1987, " Revised Cable Pulling Test".

14. Memorandum from J
8. Hosmer (TVA) to M. R. Harding (TVA) dated July 29,1987, "Sequoyah Nuclear Plant (SQN) - Units 1 and 2 - Revised '

Response to Cable Pulling Concerns" (RIMS No. .

825 870729 028).

SQEP-EEB, 0054E

KF 2 7 - N6W fq1 o-( ti STI-33 Page 15 6.0 INSTRUCTIONS (continued) 6.3.10 Reconnect the cables lifted in step 6.1.2 in accordance with M&AI-4, M&AI-6, M&AI-7, M&AI-9 and MI-6.20. QC inspection is required.

~

/

Cognizant Engineer Date 3 s NOTE:

l S All affected 480V Reactor MOV board breakers will be d y u

returned to the desired operating status as required by Operations during the performance of each functional test.

( 4' j w, Ni g G 6.4 Functional Test ~

h f NOTE:

1 q u PRIOR TO FUNCTIONAL TESTING A BRIEFING CONTAINING i

6 t ,r SPECIFICS OF EACH FUNCTIONAL TEST WILL BE CONDUCTED AND

\  % 'h RECORDED ON ATTACHMENT 3. ADD ATTACHMENT 3 PAGES AS S REQUIRED TO THE DATA PACKAGE. EACH FUNCTIONAL TEST

  1. .p g (6.4.1 FOR IT.THRU 6.4.+2-)

C g3SHALL HAVE AN ATTACHMENT 3 COMPLETED N.

'o

)h PREREQUISITE:

Obtain a waiver from the Mechanical Engineering Test Section to waive the test requirements of SI-158.1 for valve 1-FCV-70-140.

' .c / 'I Cognizant Engineer s{3 Date v r '> Engineering Test Date dd PRECAUTIONS: 1. -

a

$Q Operate valves per instructions and precautions of SI-166.6.

NN s

  • 7 e 2.

.i. '! f -(yN Functional tests 6.4.1 through 6.4.12 may be i performed in any sequence at Test Director's T- discretion, except 6.~4.6 must be performed prior to 6.4.4 3.

dV ( If a valve falls to drive in the correct direction, or falls to drive in either direction, cease testing M and determine the malfunction cause. Reestablish the hold order and correct the malfunction per Maintenance and QA instructions, perform retest as '

required.

CAUTION:

Should a valve drive in the open direction immediately stop the valve travel and secure from testing. Serious .

damage to the valves driving mechanism may occur if the valve is permitted to drive fully open. (Limit and 04660/dar torque switches will not function per design.)

< d

fcf 97- N N

l. SQN pap 8a-(Z.I STI-33 Page 18 Revision 0

.6.0

_ INSTRUCTIONS (continued) 6.4.3 Component Coolino System Pumps 2A-A and 28-8 to C-5 Pump Inlet Isolation Valve 2-FCV-70 Cable 2V2550B .

Reference drawings: 45N2750-10. -23, -27: 45N779-13 6.4.3.1 Notify the Unit Operator that the following equipment will be affected during this functional test:

1. 2-FCV-70-76

/

Cognizant Engineer Date 6.4.3.2 At valve 2-FCV-70-76, place the declutch lever in " MANUAL", and using the handwheel, position the valve to approximately its mid-travel position.

/

Cognizant Engineer Date 6.4.3.3 Request the Shift Engineer (SE) to release the hold order and energize the 480V Reactor MOV Board 282-8 compartment 14A breaker.

/ I Cognizant Engineer Date 6.4.3.4 At the local control station JB648, stroke valve 2-FCV-70-76 by depressing 2-HS-70-76B "CLOSE", then "STOP". Visually observe that valve drives in the closed directi VAwe To DRIVE FOLLY WSEO.on. So 407 Attov NOTE:

Consult Operations for approximate maximum allowable stroke time.

/

Cognizant Engineer Date i

6.4.3.5 .

Notify the Unit Operator that system may be L returned to its desired configuration status. .

UnitOpe(tor

/

Date

~

M,# +

/

04660/dar Cognizant Engineer Date

~

Icn 9 7- sy8 7 SON FY STI-33 Page 22 Revision 0 6.0 INSTRUCTIONS (continued) 6.4.6.3 Request the Shift Engineer (SE) to release the hold order and energize the 480V Reactor MOV Board 182-8 compartment 2B breaker.

/

Cognizant Engineer Date 6.4.6.4 At the local control station JB1408, stroke

",, valve 1-FCV-3-126B by depressing l-HS-3-126B/B "CLOSE", then "STOP". Visually.

observe that valve drives in the closed direction.

/

Cognizant Engineer Date 6.4.6.5 Notify the Unit Operator that the system may be returned to desired ope"ating status. .

,+'-

Cognizant Engineer Date 6.4.6.6 Perform SI-166.6 for valve 1-FCV-3-1268.

Attach copies of completed SI data sheets to the Data Package.

/

Cognizant Engineer Date 6.4.7 Comoonent Cooling System Pump 1A-A to 18-8 Suction Isolation Valve 0-FCV-70-34 Cable IV32208 Reference drawings: 45N1750-9, -23, -27: 45N779-40 6.4.7.1 Notify the Unit Operator that the following equipment will be affected during this functional test: 1

1. 0-FCV-70-34

-]

\

Cognizant Engineer Date 6.4.7.2 At valve 0-FCV-70-34, place the declutch lever in " MANUAL", and using the handwheel, j

pos)tlon the valve to approximately Its .

mid-travel positlon.

/

0466Q/dar

  • 5

f Cf 2 7- N @ Y SQN STI-33 f f- /0 o [ ~2. I Page 28 Revision 0 6.0 INSTRUCTIONS (continued) .

6.4.12.1 Notify the Unit Operator that this functional test is to be performed in conjunction with the requirements of SI-166.6 and shall immediately precede stroke time testing of ~

valve 1-FCV-62-138B.

/

Cognizant Engineer Date 6.4.12.2 At valve 1-FCV-62-138B, place the declutch lever in " MANUAL", and using the handwheel, position the valve to approximately its mid-travel position.

/

Cognizant Engineer Date 6.4.12.3 Request the Shift Engineer (SE) to release the hold order and energize the 480V Reactor MOV Board 181-B compartment 8E breaker.

/

Cognizant Engineer Date 6.4.12.4 At the local control station JB1446, stroke valve 1-FCV-62-1388 by depressing 1-HS-62-138B "CLOSE", then "STOP". Visually observe that valve drives in the closed 3 direction. /

6.4.12.5 c 7~a.s s ,A,u. ce.

Notify the Unit Operator that the system may be returned to desired operating status. '

/

Cognizant Engineer Date 6.4.12.6 Perform SI-166.6 for valve 1-FCV-62-138B.

Attach copies of completed SI data sheets to the Data Package.

/ l Cognizant Engineer Date 1 04660/dar ,

~

f6c*-(7 /4 W" i gnu.

STI-33 p a p it o b l Page (NGO)

Revision 0 6.0 ' INSTRUCTIONS (continued) j f

6. 4. 13 da. 7,9 A . ia tv. - . - f/s , vala

/-pcv.gz.97 Cable: / v 2.2. Y o 4 Reference drawings:

vr/>v71 2.3j /rA>/7 ro - 3, fg

6. 4 J3.1 Notify the Unit Operator that the following equipment will be affected during this functional test:

1,

/- Ac v- 42 '77

/

Cognizant Engineer Date _

6. 4./3. 2 A t va l ve /- rcV-n -17 place'the declutch lever in " MANUAL", and using the handwheel, position mid-travel theposition.

valve to approximately its i 7 /

( 6.4./J.3 Cognizant Engineer Date Request the Shift Engineer (SE) to release the hold order and energize the 480V Reactor i MOV Board /B/-4 compartment 9A breaker.

/

Cognizant Engineer Date

6. 4 /3. 4 At the local control station JB/rf7, stroke

valve "CLOSE", /-* then 42 77 by depressing / //s-ts. ??B "STOP".

Visually observe that VALV2 valve drives in the closed direction. DD* A/0 i NOTE: fua Y Operations Consult CLOSED for If E17//EA cEArrAZh/ML.!

approximate maximum allowable stroke time. CNM6IA/C po n g y,$  !

Cognizant Engineer

/

OPEAAI S .

Date 6.4.0.5 Notify the Unit Operator that system may be -

returned to its desired configuration status.

/

Unit Operator Date _

Cognizant Engineer ~

Date

I tc f 87- /v eY

! p" ape. I4 of Ll son STI-33 Page 33 Revision 0 DATA PACKAGE Test Data Sheet Page 4 of 19 CONDUIT MC14938

_ ITEM NO. Cable Disconnect List

8. -

Cable IV2544B, T1, T2 and T3 conductors at 1.

480V Rx MOV Bd 182-B, Compartment 10E (dwg 45N1750-9)

2. 1-FCV-70-64 (spliced)

(dug 45N1750-23) 9.

Cable IV25508, T1, T2 and T3 conductors at 1.

480V Rx MOV Bd 182-B, Compartment 14A (dwg 45N1750-10)

2. 1-FCV-70-74 (dwg 45N1750-23) 10.

Cable IV2000B, T1, T2 and T3 conductors at 1.

480V Rx MOV Bd 1B2-B, Compartment 3C (dwg 45N1750-6)

2. 1-FCV-67-82 (spliced)

(dwg 45N1750-22) 11.

Cable IV2100B, T1, T2 and T3 conductors at 1.

480V Rx MOV Bd 181-B, Compartment 8C (dwg 45N1750-3)

2. 1-LCV-62-136 (dwg 45N1750-13) 12.

Cable IV2975B, T1, T2 and T3 conductors at 1.

480V Rx MOV Bd 181-B, Compartment 8E (dwg 45N1750-3)

2. 1-FCV-62-138B (dwg 45N1750-13)

,3 _ 61dle N2 2/o8, ri, 7 z, n / 73

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2. .

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    • 9%j'a r

/

Cognizant Engineer Date 0473Q/1ds

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SON $4C 7 6(bCF Ki '

STI-33 Page 40 Revision 0 DATA PACKAGE Test Data Sheet

-, Page 11 of 19

{

j EQUIPMENT RESTORATION LIST Equipment Identification Return to Service Configuration Log Testing Complete .

Ecuioment Restored EntryClearej/4 sten 6.4. W_ r Cocnizant Encr/Date Coanizant Enne/Date CCS Pumps 2A-A to 28-B Suction Isolation Valve 0-FCV-70-39 fed from 480V Reactor MOV Board 282-8 Compartment 11C Circuit Breaker to isolate Cable'2V3220B.

CCS Pumps 2A-A d.nd 28-8 to C-S Pump Inlet Isolation Valve 2-FCV-70-78 fed from 480V Reactor MOV Board 282-8 Compartment 10E Circuit Breaker to isolate Cable 2V25448.

CCS Pumps 2A-A and 28-8 to C-S Pump Inlet Isolation Valve 2-fCV-70-76 fed from 480V Reactor MOV Board 2B2-8 Compartment 14A Circuit Breaker to isolate Cable 2V2EE0B.

ERCW Header 18 Isolation Valve 1-fCV-3-126A for 18-B MDAF Pump fed from 480V Reactor MOV Board 182-8 Compartment 2C Circuit Breaker to isolate Cable IV29409.

Reactor Coolant Pump Oil Cooler Return Containment Isolation Valve 1-FCV-70-140 fed from 480V Reactor MOV Board 182-8 Compartment ISC Circuit. Breaker to isolate *

[Able IV2989B.

0474Q/vif

scF 97 -MS'+

SQN , /19E M d 11 STI-33 Page 41 Revision 0 DATA PACKAGE Test Data Sheet

.- Page 12 of 19 EQUIPMENT RESTORATION LIST Conduit MC14938 Equipment Identification Return to Service Testing Complete Configuration tog Entry Cleared .

_Eauioment Restored Stoo 6.4.larlk Coonizant Encr/Da t e Coanirant Enc r/Da t e ERCW Header 18 Isolation Valve 1-FCV-3-1268 for 10-8 MOAF Pump fed from 480V Reactor MOV Board 182-8 Compartment 2B Circuit Breaker to isolate Cable *1V29608.

CCS Pumps lA-A to 18-B Suction Isolation Valve 0-FCV-70-34 f ed f enm. <:90V Reactor MOV Board 182-1 Compartment 11C Circuit Brecker to isolate Cable IV32208. __

CCSPumpsIA-AandIB-8t4 C-S Pump Inlet Isolation Valve 1-FCV-70-64 fed from -

480V Reactor MOV Compartment 10E Circuit Breaker to isolate \

Board 182-(t<\

Cable IV25448.

_(+

CCS Pumps 1A-A and 18-8 to k C-S Pump Inlet Isolation Valve \

1-FCV-70-74 fed from 480V \

Reactor MOV Board 182-8 't Compartment 14A Circuit k

Breakers to isolate Cable IV25508.

Aux Bldg ERCW Supply Header 18 Isolation Valve 1-FCV-67-82 fed from 480V Reactor MOV 182-0 Compartment 3C Circuit l Breaker to isolate

  • Cable IV20008.

0474Q/vif 1

i kl!!

l l

u________

l 1

  • s.

$ sf T* /L/ @Y SON STI-33 Page 42

[Of /3 o[D j 1

Revision 0.

DATA PACKAGE Test Data Sheet J Page 13 of 19 j 1

Conduit NC14938 EQUIPMENT RESTORATION LIST f i

Equipment Identification Return to Service Testing Complete Configuration Log Entry Cleared -

_Eauioment Restored Eten 6.4. R k_

Coonizant EM e/Date _ A ccirant Ena Charging Pump Suction from r/D a t e Refueling Water Storage Tank Valve 1-LCV-62-136 fed from 480V Reactor MOV Board 181-B Compartment 8C Circuit Breaker t o i s'ol a t e Ca bl e IV21008.

Emergency Boration Isolation Valve 1-FCV-62-1388 fed from 480V Reactor MOV Board 181-B Compartment 8E Circuit Breaker to isolate Cable IV29759.

CamrL9 Av-p t% flow Vnk f.fev.4;."?? OA f~~ WoV ha c.& Nou 4"d /8/-6 Ca pf M Cosw il b e de r.

/d Uale M. Mk /v 2 2 steg 9

3 0474Q/v1(

l SQN STI-33 lbf 27 -/91'f l\

/ P // o f 2/ i Page 45 DATA PACKAGE TEST DATA SHEET

{

Page 16 of 19  !

I. Conduit & Cable Data Conduit Number MC14938 Conduit Size and Material 4A '

INSUL. THICKNESS CABLE NO. MARK No. TYPE INSULATION TYPE (INCHES)

1. 2V32208 WLC 3c12 CPJJ
2. 0.030 2V2'5448 WLC 3cl2 CPJJ
3. 0.030 2V25508 WLC 3cl2 CPJJ 4 0.030 IV2940B WLC 3c12 CPJJ
5. 0.030 IV2888B WLC 3cl2 CPJJ
6. 0.030 IV2960B WLC 3cl2 CPJJ
7. 0.030 IV3220B WLC 3cl2 CPJJ
8. 0.030 IV2544B WLC 3c12 CPJJ 9.

0.030 IV25508 WLC 3cl2 10, 1V20008 CPJJ 0.030 WLC 3cl2 CPJJ 0.030

11. IV21008 WLC 3cl2 CPJJ 0.030
12. IV2975B WLC 3cl2 CPJJ 0.030 13 /Vz2ves tx c 3 c/1. O'7J 0. DO 5

0475Q/lds l

SQN id f 07 /YQ 5/

STI-33 87 "#/ 1/

Page 48 Revision 0 DATA PACKAGE Test Data Package Page 19 of 19 II. Cable Routing Data Connection Diagram Cable No. IV21008 i

From: 480V Reactor MOV Bd IB1-B, Cmprmt 8C, RA4/749 To: 1-LCV-62-136, UA3/669 45N1750-3 Con.dult Routing: IPL6516B, MC14938, IV20098 45N1750-13 Tr'ay Routing: HK-8, HL-B For: Power Supply to Charging Pump Suction From Refueling .

Water Storage Tk Valve 1-LCV-62-136

.;ble No. IV2375B From: 480V Reactor MOV Bd 181-B, Cmprmt 8E, SA4/749 To: 1-FCV-62-1388, VA4/690 45N1750-3 Conduit Routing: 45N1750-13 IPL31928, IPL31288, IV21808, IV2181B, I 1PLl5168, MCl4938, MC15318 Tray Routing: HK-B, HL-B, FI-B For: Power Supply to Emergency Boration Isolation Valve 1-FCV-62-138B t ca b k. AJs. /V nYo A G . 4 e o t/ b a c. 4 n hv 4</ tal- 8 pnf e/l 95w/7CO-* 3

/ - F C U - 6 T. 7 7 <r sw/ 7 CD - &/A Co*,c/o;f &f  : /Pl d5~/Sd, Mc /Y? 3/3, IS3/2 " #l*'b7 7 % y 4 ~/iQ : HK G, NL - /3 .

fac : pnu supp/ A- ch y.y Pe~/o n ~ ~ fY~ W h-7

/- f cV- 4 2 7) 0475Q/ Ids

JCF-87/yW '

~

S I-33 Page 52 Attachment 2 Page 2 of 2 LIST OF EQUIPMENT AFFECTED DURING DC HIGH VOLTAGE TEST OF

__ CABLE NO. SCHEMATIC NO. .

DESCRIPTI0fl IV2100B 45N779-12 Charging pump suction from refueling '. vater storage tank valve 1-LCV-62-136

, 45N657-4 Separation Relays 112EX & 112EXA 45H779-11 Voluma Control Tank Outlet Isolation Valve 1-LCV-62-132 IV2975B 45N779-24 Emergency boration isolation valve 1-FCV-62-1388

/V22vd4  %^U 77'7- 23 c 4ery7 Av Af > ~ a % [/ ~ 1/a /ve-

/- fc v - t2 ~ 77 9

1 l

047SQ/1ds s I

l l - - - - - - __---------_u

4 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT

~

SPECIAL TEST INSTRUCTION STI-33 DC HIGH VOLTAGE TEST FOR SELECTED lE CABLES WITH POTENTIAL FOR CABLE PULLBY DAMAGE CONDUIT MC14938 Units 1 and 2 Revision 0 SAFETY RELATED IN ACCORDANCE WITH STI-l /YES O NO PREPARED BY: Carlos Bordo/Chandran Bala RESPONSIBLE SECTION: DNE-EEB REVISED BY: N/A SUBMITTED BY: . \ .W- flil~.]b:,f$l-Responsible Section Supervisor PORC REVIEW DATE: AUG 151987 APPROVED BY:

Plant Manager DATE APPROVED: AUG 151gR7 FINAL PORC REVIEW REQUIRED? O YES / NO j Reason for revision (include all Instruction Change Form Nos.):

New instruction prepared to perform a DC high voltage test as described in .

STI on selected IE cables to alleviate concerns regarding cable damage.

9 l

l SEQUOYAH NUCLEAR PLANT g PLANT INSTRUCTION REVISION LOG SPECTIAL TEST INSTRUCTION STI-33 REVISION Date Pages REASON FOR REVISION (INCLUDE COMMITMENTS AND LEVEL Acoroved Affected ALL ICF FORM NUMBERS)

New instruction prepared to perform a DC high voltage test as described in STI on selected IE cables to alleviate concerns regarding cable 0 All damage.

4lk {

l i

i l

I i

l 1

1573C/1ds i

Y 0,

T0: Controlled Manual Holder FROM: Document Control / Records Management, SON -

DATE:

SUBJECT:

TRANSMITTAL OF SEQUOYAH INSTRUCTIONS Please sign below and return to acknowledge receipt of the following material and affirm that it has been placed in the appropriate manuals, your tabl.e of contents has been updated, and the superseded instruction removed and discarded. Return this transmittal to Document Control within 10 days.

STI-33 DC HIGH VOLTAGE TEST FOR SELECTED 1E CABLES WITH POTENTIAL FOR CABLE PULLBY DAMAGE CONDUIT MC14938 Units 1 and 2 Remove and Destroy Page Insert Date Revision Page Date Revision

_________________-------------------- All 0

Return to: Document Control / Records Management, Sequoyah Nuclear Plant Signature /Date 1573C/lds i

, SQN STI-33 Page 1 Revision 0 Data Package Cover Sheet Page 1 of 1 #/#YA Test Performer: 194< Date/ Time Started P /87 /6.'06 Test

Description:

Perform a DC high voltage test on selected IE cables.to -

alleviate concerns regarding possible cable damace due to cable pullbys in conduit.

MI, SI, etc., data sheets:

Were all acceptance criteria met? O Yes D No (if no explain)

Explanation:

E Were any deficiencies found? O Yes a No (If yes attach deficiencies log or identify in the Remarks section).

Remarks:

1 _.

Test Performer:

  • Date/ Time Ended Reviewed By:

/

Cognizant Engineer Date

( Approved By:

/

i 1 Responsible Supervisor (DNE) Date

. Reviewed By: .

/

QA Staff Date i=

l Final PORC review and approval (N/A if not required by STI cover sheet) '

/

PORC Chairman Date i Send to plant Master Flies for permanent rytention as a:

5 QA record in accordance with AI-7 0 Non-QA record 04660/dar

l i

SON STI-33 Page 2

) Revision 0 1.0 OBJECTIVE AND RESPONSIBILITY

~

1.1 Objective The objective of this Special Test Instruction (STI) is to demonstrate, by performance of DC high voltage tests, the integrity of selected representative it cables installed in conduits. The test is being performed to satisfy concerns identified by the Nuclear Regulatory Commission (NRC) in their Technical Evaluation Report (TER) on Sequoyah Nuclear Plant (SQN) cable pulling concerns.

These concerns address the potential for possible cable damage due to cable pullbys. To demonstrate the integrity of cables subjected to potential damage, a statistically determined sample of cables will undergo DC high voltage tests, following the introduction of water into the conduit. The test program outlined in references 2.1.1 and 2.1.2 has been evaluated by DNE and was determined to have no short or long term effects on

, the cables or raceways involved.

Successful completion of this test program on representative 1E cables will demonstrate the adequacy, with respect to the issue identified above, of all cables previously installed at SON.

The integrity of future cable installations will be ensured by the use of updated applicable installation procedures.

1.2 Responsibility The preparer (or other DNE personnel designated by the Responsible Section Supervisor) of this special test instruction is designated as the Test Director, having full >

responsibility for coordination at the test location and for the conduct of the test. The preparer is responsible for the

  • technical adequacy of the special test instruction.

Coordination and the direction of the performance of this special test shall be implemented through the supervisory personnel of all groups involved.

2.0 REFERENCES

2.1 Source Documents 2.1.1 Letter from R. L. Gridley to USNRC dated April 8, 1987, "Sequoyah Nuclear Plant (SQN) - Cable Test Program" (L44 -

870408 802) 2.1.2 Memorandum from J. B. Hosmer (TVA) to M. R. Harding (TVA) 825 870729 028, dated July 29,1987, "Sequoyah .

Nuclear Plant (SQN) Units 1 and 2 - Revised Response to Cable Pulling Concerns" 04660/dar

' i

i SQN STI-33 Page 3 Revision 0

2.0 REFERENCES

(continued) 2.2 References 2.2.1 STI-1, "Special Test Instructions" 2.2.2 AI-3, " Clearance Procedure" 2.2.3 AI-4, " Preparation, Review, Approval and Use of Plant Instructions" 2.2.4 AI-7, " Recorder Charts and Quality Assurance Records" 2.2.5 AI-12 (Part I), " Corrective Action" 2.2.6 AI-31, " Control of Measuring and Test Equipment" 2.2.7 AI-37, " Independent Verification" 2.2.8 AI-47, " Conduct of Testing" 2.2.9 M&AI-4, " Installation of Control, Power, and Signal Cables" 2.2.10 M&AI-5, " Installation of Conduit and Junction Boxes" 2.2.11 M&AI-7, " Cable Terminations, Splicing, and Repairing of Damaged Cables" 2.2.12 M&AI-9, " Tightening, Inspection, and Documentation of Bolted Connections" P. 2.13 M&Al-13. " Electrical Pressure Seal, Firestop Barrier, ,

Thermo-Lag 330 Fire Barrier System and Flame Retardant Cable Coating" 2.2.14 TI-76, " Electrical Maintenance Post-Maintenance Testing" 4

2.2.15 IEEE Standard 383-1974, "IEEE Standard for Type Test of Class lE Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations" 2.2.16 SQM1, 'lequoyah Nuclear Plant Maintenance Program" 2.2.17 SQM2, " Maintenance Management System" '

2.2.13 MI-6.20. " Configuration Control During Maintenance Activities" 2.2.19 SOA66, " Plant Housekeeping" 04660/dar 1

l

_~. . - - _ - . - -___- -- .- - - _ _ -__.-___-__ -_--_ - - _

(

SQN l

STI-33 H Page 4 i,

l Revision 0 A.

2.0 REFERENCES

- (continued) 2.2.20 PAYSI-13 " Fire" 2.2.21 Memorandum from J. A. Kirkebo (TVA) to S. A. White (TVA) 843 870407 901, dated April 9.1987, " Effects of "

Introducing Water into Conduits for the Purposes of Performing High-Voltage Tests.on Cables" J. 2.2.22 SI-166, "Sumr.ar/ of Valve Tests for ASME .Section XI" 2.2.23 SI-166.6, " Testing of Category "A" and "B" Valves After Maintenance or Upon Release From a Hold Order"

l. 2.2.24 DRAWINGS 1

'-- Drawing No. Rev. Title 45N657-4 L Separation & Misc Aux Relays Schematic Diagrams. Sheet 4 l

45N765-6 M 6900V Shutdown Aux Power Schematic i

Diagrams Sheet 6 45N779-11 S 480V Shutdown Aux Power Schematic

? Diagrams Sheet 11 45N779-12 T 480V Shutdown Aux Power Schematic Diagrams Sheet 12 45N779 HH 480V Shutdown Aux Power Schematic Diagrams Sheet 13 45N779-23 Q 480V Shutdown Aux Power Schematic *i Diagrams Sheet 23 45N779-24 Y 480V Shutdown Aux Power Schematic i Diagrams Sheet 24 45N779-35 R 480V Shutdown Aux Power Schematic Diagrams Sheet 35 45N779-40 H 480V Shutdown Aux Power Schematic Diagrams Sheet 40

~

45N1750-3 H Unit 1 480V Reactor MOV Board 1B1-B Connection Diagrams Sheet 3  ;

45N1750-6 E Unit 1 480V Reactor MOV Board .

182-B Connection Diagrams Sheet 1 i 0466Qldar 1

)

{

- _ _ _ _ _ _ - _ _?_ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ^ - - ^ - ^ ^ -

SON STI-33 j

Page 5 Revision 0

2.0 REFERENCES

(continued) 2.2.24 DRAWINGS (continued) 45N1750-9 E Unit 1 480V Reactor MOV Board .

182-8 Connection Diagrams Sheet 4 45N1750-10 C Unit 1 480V Reactor MOV Board 182-B Connection Diagrams Sheet 5 45N1750-13 J Unit 1 480V Reactor MOV Board 181-B Connection Diagrams Sheet 7 45N1750-15 H Unit 1 480V Reactor MOV Board 181-B Connection Diagrams Sheet 9 45N1750-16 G Unit 1 480V Reactor MOV Board 181-B Connection Diagrams Sheet 10 45N1750-21 I Unit 1 480V Reactor MOV Soard 182-B Connection Diagrams Sheet 7 45N1750-22 G Unit 1 480V Reactor MOV Board 182-B Connection Diagrams Sheet 8 45N1750-23 I Unit 1 480V Reactor MOV Board 1B2-B Connection Diagrams Sheet 9 45N1750-24 A Unit 1 480V Reactor MOV Board 182-B Connection Diagrams Sheet 10 45N1750-26 E Unit 1 480V Reactor MOV Board 182-B Connection Diagrams Sheet 12 ,

45N1750-27 B Unit 1 480V Reactor MOV Board 182-B Connection Diagrams Sheet 13 45N2750-9 D Unit 2 480V Reactor MOV Board 2B2-B Connection Diagrams Sheet 4 45N2750-10 E Unit 2 480V Reactor MOV Board 282-B Connection Diagrams Sheet 5 45N2750-23 N Unit 2 480V Reactor MOV Board .

2B2-B Connection Diagrams Sheet 9 45N2750-27 E Unit 2 480V Reactor MOV Board 2B2-B Connection Diagrams Sheet 13 0466Q/dar

1 SQN 7

STI-33 Page 6 Revision 0

-s .3.0 PREREQUISITES

~

3.1 -- This special test instruction requires the issuance of a work request as per SQM2. Work request number BS98227 issued.

'fo-.%3 & I hWcPP

  • Cognizant Engineer Date 3.2 Sequoyah Nuclear Plant, Units 1 & 2, shall be in Mode 5, Cold Shutdown, for'the performance of this test.

TM / MD.

Cognizant Engineer Date 3.3 The Maintenance and Surveillance Scheduling Section has been notified of the performance of this test.

, / A .2 '

' ' ~

MSS # ~Date 3.4 The Shift Engineer (SE) has been notified and his authorization obtained for the performance of this test.

A l hl b

/ShifMngineer IDite ~ Timef 3.5 A copy of this instruction, including any and all approved changes, shall.be located in th on o room to inform the Unit Operators of the test scope.

/J,ff /4N I V (fni t'V7 'rTtor Date

( UWit '24pefator

/ / b/2 h? '

Date 3.6 Obtain a radiation work permit (RWP) for work required within a radiological control area. N/A step signoff if RWP is not JYkb

' Cogntiant Engineer IPb3/77

'Date 3.7 The Test Director shall verify that all personnel involved with  !

the performance of this test have been trained and understand their responsibilities during the performance of this test. A -

copy of the training roster of personnel who have been trained shall be attached to each completed Data Package. Refer to jf6/9& k j e a.e) 04660/dar TestDi/rfctor Date

t

j. ,,

TCP97-15U hC,E 30F3

' SQN

/ STI-33 Page 7 Revision 0

_ 4.0 PRECAUTIONS AND LIMITATIONS 4.1 The area around the exposed ends of the cables under test must be roped off or isolated by means of orange tape and caution signs.

~4.2 a Only authorized testing and support personnel shall be allowed .

1: within the roped off test boundaries while the test is in progress.

v 4.3 7 @4 j Personnel shall be stationed in the area of the exposed ends of t

i the test intocable while the test is in progress, to preclude any YV$ entry the test boundary.

U w4 6 4.4 Cable testing must be scheduled and coordinated so that at no time 7

4 I will both trains of safety related equipment (Train A and Train B) be placed in an inoperable condition.

. g $ [q 4,g The redundant train shall be verified operable prior to removing equipment from service.

w 1

+hE 5's ? 4.5 Any deficiencies found during the conduct of this test shall be

$0ERi documented on the test Deficiency Log, page 15 of the Data Package

,( ug(y

.I o 4.6 Test equipment used in the conduct of this test shall be

~)yi N documented on the Special Test Equipment Log, page 14 of the Data Package.

i .

) 3 k h, 4.7 When working near energized electrical equipment, use extreme g caution to minimize the possibility of electrical shock or burn

.((o g from occurring.

U [ N.k 4.8 Temporary measures will be used within this instruction to 4 4 minimize and contain water leakage as applicable.

% ..Should N.hbeh'- tq% $ M3$. inadvertent

  • water, leakage occur,o the: Test
  • Director shall ',

32 9NQ gA -5/ M immediately initiate steps to secure'high potential testing . ,

9 and initiate work requests as required for cleanup activ ,

$% $ @;T $*

9 4.9 E[N I M- Common Mode Failure - Redundant Measuring and Test Equipment MbM .

(M&TE) may be used after calibr'ation is vertfled (it shall be

_f$kkh assumed that the M&TE was used for Train A prior to this test).

Reference SQM1 and AI-31.

+A%b' T.A W 5~ 1 10 .

T U Testing of the first cable to be tested shall commence within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of completion of the water injection per source document 2.1.2, enclosure 2.

kil So the equipment in this STI are the same as pose-1TI ~

STI-34. In or STI, STI-33 and STI-34 muse able to perform functional tests in this completed indene perfgf me Mda cii...other. MI ere 6 and functional test e 5Il-33 M i be completed before STI-34 or vise versa. *

} 04660/dar -

t  ;-

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-. 5.0 SPECIAL TEST EQUIPMENT 5.1 Portable DC high voltage test set, Associated Research model. l number AR5220. R 5.2 Stopwatch - Meylan (or other manufacturer) e 1.5 s/hr accuracy. -

5.3 Voltmeter - Fluke model 8600A or equivalent.

6.0 INSTRUCTIONS NOTES: 1. All configuration changes will be performed using Maintenance Instruction, MI-6.20. Copies of MI-6.20 sheets generated due to this procedure shall be attached to the Data Package.

2. The reinstallation of equipment will be performed using.

approved plant procedures. All QC holdpoints as outlined in the approved plant procedures are applicable and shall be inspected by a QC inspector. Copies of data sheets generated due to this test instruction shall be attached to the Data Package.

3. A Chronological Test Log as required by AI-47 shall be kept with the Data Package using as many sheets as needed of Attachment 5.
4. A visual inspection of each valve is to be performed prior .

to stroking them to ensure no physical obstructions are present which may result in damage to the valve.

6.1 DC High Voltage Test N_0TE: Temporary measures such as, but not limited to, taping

  • and/or sealing of conduit joints, wrapping of conduits, and covering of equipment and components in the surrounding area, as noted in the following steps, are being performed to minimize and contain water leakage.

Selected conduit segment will have water introduced into the conduit at selected location as shown on the sketch of Attachment 4. During the sealing and protection  ;

process, changes may be required to the sketch due to '

field conditions. The Test Director and QC shall initial and date all changes to the sketch to verify that the intent of this instruction is not changed. -

6.1.1 Verify equipment shown on pages 1 and 2 of the Data Package is out of service and the proper hold order is in {

effect. Sign off on pages 1 and 2 of the Data Package. ,  !

NOTE 1: Refer to Attachment 2 for list of equipment affected during DC high voltage tests of cables.

0466Q/dar

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~ - 6.0 INSTRUCTIONS (continued)

NOTE 2: Equipment on pages I and 2 of the Data Package is the minimum required for performance of this test instruction. -If,

.due to field configurations, additional .

equipment. clearances are required to safely introduce water for testing, that equipment shall be added to pages 2 and 13 of the Data Package and the appropriate sign-offs obtained on page 2 prior to testing.

NOTE 3: Cables 2V2544B, IV25448 and IV20008 are spliced at their respective valve end.

Determinate per instructions in M&AI-7.

6.1.2 Verify that each conductor of the cables shown on pages 3 and 4 of the Data Package are labeled or color coded, and laid down per the as-configured (as-constructed) drawings. Then verify they are deenergized and disconnect them per MI-6.20.

6.1.3 Remove' junction box JB1002 cover shown on the sketch of Attachment 4 (Log in MI-6.20).

6.1.4 Inspect accessible portions of cables for physical damage. Visually inspect for conduit fire / pressure seals between water injection point and drain point as shown on the sketch of Attachment 4. Breach barriers (per_M&AI-13 and PHYSI-13) as required to allow the introduction of water into conduit MC14938. Any deficiencies shall be documented on the test Deficiency Log, page 15 of the Data Package. ,j 6.1.5 Seal conduit joints shown on the sketch of Attachment 4 l to keep water leakage to a minimum. (Log in MI-6.20.).

Install protective materials as needed at junction box JB 1002 to control the accumulation or flow of water. rl CAUTION:

Care is to be exercised not to allow the 4 water to come in contact with the energized f electrical equipment and internal board components. This may be accomplished by temporarily covering panels, boards, switchgear, motors, etc. However, temporary ,

l covering shall not be installed directly on vent openings or in such a way that the covered equipment will be subjected to higher-than-normal temperatures. -

SQN STI-33 Page 10

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~-- 6.0 INSTRUCTIONS (continued)

HOLDPOINT:

The Test Director shall verify by inspection that steps 6.1.1 through 6.1.5 have been completed prior to the injection of water.

TestDirecfgF Date NOTE: For the intent of this test, potable water is synonymous with tap water.

6.1.6 Inject ordinary tap / potable water into the conduit at point shown on the sketch of Attachment 4 such that i

there is the presence of moisture along the entire surface of the installed cables, in the conduit segment under test. Injection may be achieved using any low pressure means depending only upon the accessibility of the field configuration.

NOTE: The cables shall be considered sufficiently wet when water injection is accomplished by one of the following methods. The Test Director shall v

coordinate the~ wetting and sign off when wetness

-/ has been achieved. Second party verification is required.

A. The conduit shall be sealed to the extent practicable. The purpose of the seals is to reduce the loss of water from the conduit when wetting the cables. Water shall be injected slowly into the conduit at a rate faster than it.is lost through conduit openings or connections until the cables are initially submersed. It is not intended or expected ,

that the cables will remain submersed.

I- B. Water shall be sprayed into the conduit under.

pressure at a sufficient number of points such that the water spray would cascade down over the installed cables. If this method is used the water spray shall be maintained at each injection point for a period of two (2) minutes or longer as required. (The time may depend on the length of the conduit section.)

N(k / 014- Q Test Director Date h

C

/ P .2 % 9 7,

  • Verified by Date

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6.0 INSTRUCTIONS (continued) I

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6.1.7 Using a suitable device such as sound powered head sets or telephones, buzzer or bell, perform a continuity check on one conductor of each applicable cable - j disconnected in step 6.1.2. Sign off for the '

conductor (s) checked and N/A remaining conductors on pages 5 through 10 of the a k Cognfzant E@ineer Date l 6.1.8 Set up the DC high voltage test set in a suitable location at the test end. The test end of the conductors shall be determined by field inspection to facilitate testing.

t'ognizant Engineef Date j

6.1.9 Ensure the conduit and the DC test set are solidly grounded to the station ground with adequate grounding straps. Using a meter, verify a reading of less than two (2) ohms to ground.

88d / P-A%P7 Tognizant Engind4r j Date 6.1.10 Ensure the other end of all conductors of the test cables are separated, taped over using a minimum of 2 laps of Scotch 33, and isolated from other conducting material by air gaps or other insulating material.

Yk Cognizant Engf6eer ISM D Date 6.1.11 Ensure that all conductors of the cables in the conduit

  • to be high voltage tested other than the test specimen are electrically tied to the conduit and connect the DC test set to the conductor under test. Sign off on pages 5 through 10 of the Data Package.

4 / I7 (pgnizantEngineef Date 6.1.12 Ensure the DC voltage setting on the test set is 0 volts and energize test set. Gradually and uniformly increase the voltage to the value specified on pages 5 through 10 -

of the Data Package in not less than 10 seconds nor more than 60 seconds using the stopwatch. Log voltage applied on pages 5 through 10 of the Data Package.

Continue the applied voltage for a duraticin of five (5) minutes using the stopwatch. Read and record the leakage current as shown on the microammeter of the DC 0466Q/dar i .t

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t--

6.0 INSTRUCTIONS (continued) i 6.1.12 (continued) l l

high voltage test set at one minute intervals for the duration of the test and record on pages 5 through 10 of

  • the Data Package.

O#,w (28W / [-3%fr7 C#gnizant Enginedr Date NOTE: Should a conductor failure occur prior to reaching the test voltage, document the value attained just prior to the failure on the Deficiency Log page 15 of the' Data Package.

6.1.13 Record the test results, pass or fail, on'pages 5 ,

through 10 of the Data Package. Refer to Section 7.0 l for acceptance criteria.

N /

Cognizant Engi l 6.1.14 After completion of the five (5) minute test gradually decrease-the voltage level to zero, and'deenergize the test set.

Then, install the high potential test set grounding stick on the test specimen and apply a ground wire to ensure all voltage charges have drained to ground. Sign off on pages 5 through 10 of the Data  ;

&[& / h .LY-27 CCognizant Engin6'er Date i

l. 6.1.15 Disconnect the grounding stick installed in step  ;

6.1.14. Sign off on pages 5'through 10 of the Data

@#dM/ 7 2 Date gBgnizantEngineef Of 7 6.1.16 Repeat steps 6.1.11 through 6.1.15 for all conductors in the cables to be tested. Reference pages 5 through 10 of the Data Package.

(26gnizant Enginedr Date L 6.1.17 Disconnect all grounding straps, electrical ties and the i I ground wire installed in step 6.1.9, 6.1.11, and -

l 6.1.14 Remove all electrical tape and insulating i material installed in step 6.1.10..

%9M CognizaWt Engineer

/ 2 /8 /87 Date )

1 04660/dar j l l g b

SQN STI-33 Page 13 f

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-__ 6.0 INSTRUCTIONS (continued)

NOTE: If a failure occurs, retesting may be performed per steps 6.1.8 through 6.1.15 and 6.1.17 (excluding 6.1.16) of this Instruction (Data sheets to be added as required) under the guidance of the Test Director. Any disassembly, disconnection, etc. required for this retesting shall be performed using a QA approved work ,

request. l l

6.2 Step intentionally left blank.  !

6.3 Restoration 6.3.1 Drain standing water from conduit into suitable containers and/or plant drains.

sum l Ehi//E7 Cognizant Engineer Date l NOTE:

Draining of standing water from the conduit following '

testing will leave the cables, at v>rst, in a " wet" condition. This is well within tha long-term environmental conditions for which the cable is designed and, therefore, will have no effect on the cables' integrity or their ability to perform their intended function. Het conduit will not constitute a safety hazard from electrical shock after the cable is re-energized because the insulation capability of the cable will have been verifieo by the test. Care will be exercised not to allow the water to come in contact with the energized electrical equipment.

HOLDPOINT 6.3.2 Following the draining of standing water, the conduit sections which have been wetted shall be blown down using control air.

Cart shall be exercised to contain any moisture blown throagh and out of the conduit. The Test Director shall vi',ually inspect and sign off this hold point when the cenduit has been sufficiently dried (no visible water driuping from each section within a reasonable timeframe).

% M, i Ph&7

  • Test Director Date 04660/dar s.

l~ SQN l  ; STI-33 Page 14 lj Revision 0

-. 6.0 -INSTRUCTIONS (continued)

~

6.3.3 Fire / pressure seals removed under 6.1.4 shall be reinstalled per M&AI-13 (QC inspection required) and data sheets completed. At this time, close any PHYSI-13 paperwork that was generated due to step 6.1.4.

(~ &~ . . . . , / $~26-8 7 CognizantEngingr ~ Date NOTE: Refer to the MI-6.20 sheets generated by this procedure and sign off all open items as they are completed.

6.3.4 Remove the temporary sealants installed in step 6.1.2.

6.3.5 Remove the temporary protection coverings installed in step 6.1.5.

6.3.6 Reinstall junction box cover removed in step 6.1.4.

6.3.7 The Test Director shall verify by inspection that steps 6.3.4 through 6.3.6 have been completed.

/

. Test Director Date 6.3.8 Inspect, where accessible, cablesflV2940B,*1V29608, IV28888,*1V2100B jacket and insulation for tracks, surface crazing and embrittlement.

3 rric;s4c/ss F... A Deficiencies found: Yes (Circle one) y ves @

Deficiencies Recorded in-.Qeficiency Log, page 15 of the .

Data Package. Yes @ (Circle one)

$Cthsv mu47h /dbfLY7 >,-. ell .

v ~

%-& 87 WC // Crytsman" Date 6.3.9 Inspect the operator housing for valve 1-FCV-70-140

1. Inspect gasket and clear flow path of T-drain.
2. Perform visual inspection for degradation of limit switch compartment. .

Deficiencies found: Yes h(Circleone)

Deficiencies Recorded in Defic nc Log, page 15

/. of the Data Package. Yes N/ Ircle one)

Gdd I 7 K- 77

/~ graft %Iah - Date 0466Q/dar  !

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~-

6.0 . INSTRUCTIONS (continued) '

6.3.10' Reconnect the cables lifted in step 6.1.2 in accordance with M&AI-4, M&AI-6, M&AI-7, M&AI-9 and MI-6.20. QC inspection is required & & c I 8-25-#p' '

Cogniz' ant Engirf66r' Date s NOTE:

L S All affected 480V Reactor MOV board breakers will.be 4 .y returned to the desired operating status as required by Operations during the performance of each functional g u ~~

test.

N(. S jE

_ y G 6.4 Functional Test j

1 v f u NOTE:

PRIOR TO FUNCTIONAL TESTING A BRIEFING CONTAINING 9 0 't

  • SPECIFICS OF EACH FUNCTIONAL TEST WILL BE CONDUCTED AN

'\ g 'h RECORDED ON ATTACHMENT 3.

. ADD ATTACHMENT 3 PAGES AS REQUIRED TO THE DATA PACKAGE. EACH FUNCTIONAL TEST.

j j.N (6.4.1 THRU 6.4.

g; FOR IT. SHALL HAVE AN ATTACHMENT 3 COMPLETED f,3 h PREREQUISITE:

1 Obtain a waiver from the Mechanical Engineering Test Section to waive the test io _

requirements of SI-158.1 for valve 1-FCV-70-140

,4'~,, (

( / $ # / f/Z5/97 Cognizant Eng gher Y' .{

Date -

D%'r - ' )>

W L 3 -Q MAC B Engineering Test g/ Skg/g]

Date '

d 'l PRECAUTIONS: 1.

)Q ~

Operate valves per instructions and precautions of s SI-166.6. *

'%e g N{* 2.

.i.'! * -($ Functional tests 6.4.1 through 6.4.12 may be i N performed in any sequence at Test Director's discretion, except 6.'4.6 must be performed Drlor to Y,,e t 6.4.4.

i'3' 9 [ t 3.

If a valve falls to drive in the correct direction,

(

or falls to drive in either direction, cease testing 4' and determine the malfunction cause. Reestablish the hold order and correct the malfunction per Maintenance required. and QA instructions, perform retest as ~

CAUTION:

Should a valve drive in the open direction immediately stop the valve travel and secure from testing. Serious

'- damage to the valves driving mechanism may occur if the .

valve is permitted to drive fully open. (Limit and torque switches will not function per design.)

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Page 16

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.. 6.0 INSTRUCTIONS ~' een"inued) 6.4.1. Component Cooling System Pump 2A-A to 2B-B Suction 1 Isolation Valve 0-FCV-70-39 Cable.2V32208

-{

Reference drawings: 45N2750-9, -23, -27; 45N779-40 I 6.4.1.1 Notify the Unit Operator that the following l equipment will be affected during this l functional test:

1. 0-FCV-70-39

{

Cognizant EnginWt/

18kok5 Date 6.4.1.2 At valve 0-FCV-70-39, place the declutch  !

lever in " MANUAL", and using the handwheel, position the valve to approximately its mid-travel position.

) / / /

Cognizant En%(nefr ' Date 6.4.1.3 Request the Shift Engineer (SE) to release i the hold order and energize the 480V Reactor MOV Board 2B2-B compartment 11C breaker.

.j i

WCognizant hs Engh fef ISk 'Dats

/2 6.4.1.4 At the local control station JB649, stroke *,

valve 0-FCV-70-39 by depressing 0-HS-70-39B "CLOSE", then "STOP". Visually observe that valve drives in the closed direction.

NOTE: Consult Operations for approximate maximum allowable str ke time.

If J' ff Cogni'zint Engli(pfr/ 'Datd j l

6.4.1.5 Notify the Unit Operator that system may be -

returned to its desired configuration status. j f b

// Uhlt Opef(toy I$

Date hf .i

&W Cognizant Engin Vr' Ish

'Da e 04660/dar

{ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

SQN STI-33 Page 17

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~. 6.0 INSTRUCTIONS (continued) 6.4.2 Component Cooling System Pumps 2A-A and 28-B to C-S Pump-Inlet Isolation Valve 2-FCV-70-78 Cable 2V2544B Reference drawings: 45N2750-9, -23, -27; 45N779-13 6.4.2.1 Notify the Unit Operator that the following equipment will be affected during this functional test: -

1. 2-FCV-70-78

_ C6C /7647 CognizantFgineer Date 6.4.2.2 At valve 2-FCV-70-78, place the declutch lever in " MANUAL", and using the handwheel, position the valve to approximately its mid-travel position.

l e / 7-9 %7 Cognizant ErgAneer Date 6.4.2.3 Request the Shift Engineer (SE) to release the hold order and energize the 480V Reactor MOV Board 282-B compartment 10E breaker.

[TM

~ ~

-e / 9-94"?

CognizantEn@eer Date 6.4.2.4 At the local control station JB649, stroke

  • valve 2-FCV-70-78 by depressing 2-HS-70-78B "CLOSE", then "STOP". Visually observe that valve drives in the closed direction.

NOTE: Consult Operations for approximate maximum allowable stroke time.

(

~ IQ-SA]

~

Cognizant E4efineer Date 6.4.2.5 Notify the Unit Operator that system may be ~

returned to its desired configuration status.

W Unit Operator I 76 'l?

1 Date CA?)/

I 9-[-S7 Cognizant Er[gfneer Date l L

t

  1. WE

/

STI-33 Pa e IB Revision 0 6.0 IttSTRUCTIONS (continued) 6.4.3 Comoonent Cooling System Pumps 2A-A and 28-B to C-S Pumo

. Inlet Isolation Valve 2-FCV-70-76 Cable 2V2550B .

Reference drawings: 45N2750-10, -23, -27: 45N779-13 6.4.3.1 Notify the Unit Operator that the following

~

equipment will be affected during this  ;

functional test:

1. 2-FCV-70-76 RQ / E'/2m /27 Cognizant Engineer Date 6.4.3.2 At valve 2-FCV-70-76, place the declutch lever in " MANUAL". and using the handwheel, position the valve to approximately its mid-travel position.

RQ cr< /Phet/P/

Cognizant Engineer Date 6.4.3.3 Request the Shift Engineer (SE) to release the hold order and energize the 480V Reactor MOV Board 2B2-8 compartment 14A breaker.

9 &_ Q k _ - ~ / 8'/Jc,/O Cognizant Engineer Date 6.4.3.4 At the local control station JB648, stroke ,

valve 2-FCV-70-76 by depressing 2-HS-70-76B "CLOSE", then "STOP". Visually observe that f/-7

, pqssd valve drives in the closed directi vAwe To DruvE Futa' cloMO.on. .Do do7 ALiou N0iE: Consult Operations for approximate maximum allowable stroke time.

/

Cognizant Engineer Date ~

6.4.3.5 Notify the Unit Operator that system may be returned to its desired configuration status. .

UnitOpe(tor Date g 0466Q/dar Cognizant Engineer Date l

- _ _ - - - - _ _ _ - _ _ _ - _ _ - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = - - - - - - - - - - - - - - - - - - - - - - -

1 '

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SQN STI-33

-Page 19 i Revision 0

]

.,. 6.0 INSTRUCTIONS (continued).

i 6.4.4 Essential Raw Cooling Water System Header 18 Isolation Valve 1-FCV-3-126A for 18-8 Motor Driven Aux FW Pump.

.. Cable IV29408 Reference drawings: 45N1750-6, -21, -26;-L45N779-23 CAUTIONS: 1. To prevent introducing ERCH into the AFW system perform functional 6.4.6 for 1-FCV-3-1268 prior to functional 6.4.4 for 1-FCV-3-126A.

2. Instructions and precautions of SI-166.6 shall be followed.

6.4.4.1 Notify the Unit Operator that this functional test is to be performed in conjunction with the requirements of SI-166.6 and.shall immediately preceae stroke time testing of valve 1-FCV-3-126A.

' Q' Cognizant EngineerDate ~

l0 k //Wrob7 6.4.4.2 At valve 1-FCV-3-126A, place the declutch lever in " MANUAL",.and using the handwheel, ,

position the valve to approximately its mid-travel position.

QA Cognizant f Engineerf I Pbsl7f Date 6.4.4.3 Request the Shift Engineer (SE) to release the hold order and energize the 480V Reactor MOV Board 182-8 compartment 2C breaker.

I / P/h4[sP/

" Cognizant Engineer 'Da te ~

f.4.4.4 At the local control station JB1408, stroke valve 1-FCV-3-126A by depressing 1-HS-3-126A/B "CLOSE", then "STOP". Visually observe that valve drives in the closed -

direction.

0^1CognizaBT Engineer A ~

I Wyek?f Dat( '

0466Q/dar

SQN STI-33

r Page 20 g Revision 0

-- 6.0 INSTRUCTIONS (continued)

~

6.4.4.5 Notify the Unit Operator that the system may be returned to desired operating status.

I -

Cognizant Engineer Date 6.4.4.6. Perform SI-166.6 for valve 1-FCV-3-126A.

Attach copies of completed SI data sheets to the Data Package.

/

Cognizant Engineer Date 6.4.5 Reactor Coolant Pumo 011 Cooler Return Containment Isolation Valve 1-FCV-70-140 Cable IV2888B Reference drawings: 45N1750-10 -15, -21; 45N779-35 CAUTIONS: 1. To perform this functional reactor y coolant pumps should not be running.

2. Instructions and precautions of SI-166.6 shall'be followed.

6.4.5.1 Notify the Unit Operator that this functional test is to be performed in conjunction with the requirements of SI-166.6 and shall immediately' precede stroke time testing of valve 1-FCV-70-140.

&)fG Isk9k'7 Cognizaiit ' Engineer Date 6.4.5.2 At valve 1-FCV-70'-140, place the declutch lever in " MANUAL", and using the handwheel, position the valve to approximately its mid-travel position.

0 ]' Cogn'IzTift'Eng'i neerdf0ll)I 'Da t'e Eheb7 6.4.5.3 Request the Shift Engineer (SE) to release the hold order and energize the 480V Reactor MOV Board 182-B compartment 15C breaker.

I h"YC6gnizant Engineer  : I $42Q/77 Dath' 04660/dar u- _ _ _ _ - - l

SON STI-33

-Page 21

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.. 6.0 INSTRUCTIONS (continued)

~

6.4.5.4 At the local control station JB1354, stroke valve 1-FCV-70-140 by depressing 1-HS-70-140B "CLOSE", then "STOP". Visually observe that valve drives in the closed direction.

Q fMA ll W.19/P7 Cogniz'anfEngineer Date 6.4.5.5 Notify the Unit Operator that the system may be returned to desired operating status.- ,

&L , YI W27k7 Cognfzant Engineer Date 6.4.5.6 Perform SI-166.6 for valve 1-FCV-70-140.

Attach copies of completed SI data sheets to the Data Package.

Q' ACognizilit 03 I W29h/

Engineer Date ~

6.4.6 Essen,tial Raw Cooling Water System Header 1B Isolation Valve 1-FCV-3-126B-for IB-B Motor Driven Aux FW Pumo.

Cable IV2960B Reference drawings: 45N1750-6, -21, -26; 45N779-23 CAUTION: Instructions and precautions of SI-166.6 shall be followed.

6.4.6.1 Notify the Unit Operator that this functional .

test is to be. performed in conjunction with the requirements of SI-166.6 and shall immediately precede stroke time testing of valve 1-FCV-3-1268.

h 10 Cognizant Engineer IY Date '

Offf 6.4.6.2 At valve 1-FCV-3-1268, place the declutch lever in " MANUAL", and using the handwheel, position the valve to approximately its -

mid-travel position.

h f(). ) l T/Qd/Af ~

Cognizant Encfineer Date 04660/dar

____i__.________________

7ca 12 7- Jygy

pyf 'l o f '2.1 STI .

Page 22-Revision 0-l' 6.0 INSTRUCTIONS (continued) 6.4.6.3 Request the Shift Engineer (SE)_to release the hold order and energize the 480V Reactor MOV Board IB2-B compartment 28 breaker.

b , f/). Y C6gnizant' Engineer

'I9'"/Jd/5"/

Date '

6.4.6.4 At the local control station JB1408, stroke

. valve 1-FCV-3-1268 by depressing

.1-liS-3-126B/B "CLOSE"', then "STOP". Visually, observe that valve drives in.the closed direction.

} U. o I ?l~/]C/W .

Cognizant Engineer Date 6.4.6.5 Notify the Unit Operator that the system may be returned to desired ope"ating status. '

p,&

Cognizant Engineer Date 6.4.6.6 Perform SI-166.6 for valve 1-FCV-3-1268.

Attach copies of completed SI data sheets to the Data Package. I

/

Cognizant Engineer Date 6.4.7 Comoonent Cooling System Pump 1A-A to 18-8 Suction Isolation Vaive 0-FCV-70-34 g Cable IV32208

)

i Reference drawings: 45N1750-9, -23, -27: 45N779-40 I

6.4.7.1 Notify the Unit Operator that the following j equipment will be affected during this functional test:

1. 0-FCV-70-34

& sSo Cognizailt Engineef/ If2fr-ff

  • Date 6.4.7.2 At valve 0-FCV-70-34, place the declutch lever in " MANUAL", and using the handwheel,

.' position the valve to approximately its . {

mid-travel position.

WH $ I ffffy Cognizant EngifWef Date t ~

SQN STI-33

' Page 23

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- 6.0 INSTRUCTIONS (continued)

~

L 6.4.7.3 Request the Shift Engineer (SE) to release the hold order and energize the 480V Reactor-  ;

MOV Board 182-8 compartment 11C breaker. '

i

&S Cognizant Engirre(r

/Fffff Date 6.4.7.4 At the local control station JB1640, stroke valve 0-FCV-70-34 by depressing 0-HS-70-348. 5 "CLOSE", then "STOP" Visually observe that {

valve drives in the closed direction.

NOTE: Consult Operations for approximate maximum allowable stroke time.

~ Cogniza'nt EngineF YI fffA'fDate 6.4.7.5 Notify the Unit Operator that system may be

-returned to its desired configuration status.

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Cogrfizant Encf)(e(r Date 6.4.8 Component Cooling System Pumps lA-A and IB-B to C-S Pumo Inlet Isolation Valve 1-FCV-70-64 Cable IV25448 Reference drawings: 45N1750-9, -23. -27; 45N779-13 I 6.4.8.1 Notify the Unit Operator that the following equipment will be affected during this functional test:

1. 1-FCV-70-64

/9 f187 Cognizant L9(gineer Date 6.4.8.2 At valve 1-FCV-70-64, place the declutch lever in " MANUAL", and using the handwheel, i position the valve to approximately its  ;

mid-travel position. .

OE7J / N3S7 CognizantE%x ineer Date 04660/dar

$ ^

SQN.

STI-33 Page 24 Revision 0

. - - 6.0 . INSTRUCTIONS (continued) 6.4.8.3 Request the Shift Engineer (SE) to release the hold order and energize the 480V Reactor MOV Board 182-B compartment 10E breaker.

(2 I 8-2 H ]

CognizanF Engineer Date 6.4.8.4 At the local control station JB648, stroke valve 1-FCV-70-64 by-depressing 1-HS-70-648 "CLOSE", then "STOP". Visually observe that valve drives in the closed direction.

NOTE: Consult Operations for approximate maximum allowable stroke time.

/ F-29-8 7 Cognizant pilgineer Date 6.4.8.5 Notify the Unit Operator that system may be returned to tt desired configuration status.

kl I f-$if g ' UnfT ORVrator ~ Date ~

/8-29-i7 Cognizant [fgineer Date 6.4.9 Component Cooling System Pumps lA-A and 18-8 to C-S Pump Inlet Isolation Valve 1-FCV-70-74 Cable IV25508 Reference drawings: 45N1750-10, -23, -27; 45N779-13 6.4.9.1 Notify the Unit Operator that the following equipment will be affected during this functional test:

1. 1-FCV-70-74 ,

fl h.

/62987 Cognizant 6ngineer Date 6.4.9.2 At valve 1-FCV-70-74, place the declutch lever in " MANUAL", and using the handwheel, position the valve to approximately its mid-travel position.

(29]L I S .7.9 -81 Cognizant (/ Engineer Date e n

~

SQN 1

STI-33 C

Page 25

, Revision 0

- ~ . - 6.0 INSTRUCTIONS (continued) 6.4.9.3 Request the Shift Engineer (SE) to release the hold order and energize the 480V reactor MOV Board 182-B compartment 14A breaker.

h, IR,29-[r7 Cognizan @ gineer Date 6.4.9.4 At the local control. station JB648, stroke valve 1-FCV-70-74 by depressing 1-HS-70-748 "CLOSE", then "STOP". Visually observe that valve drives in the closed direction.

NOTE: Consult Operations for approximate maximum allowable stroke time.

h -

l 8-2M7 Cognizantpgineer Date 6.4.9.5 Notify the Unit Operator that system may be returned to I,ts-d sire c nf,lguration' status.

. /

Uni t'Vperstor

/ 'Date. DCfk[

7 ~

'I ' 8 ') $ M Cognizant Ers4neer Date 6.4.10 Aux Bldo Essential Raw Cooling Water Supply Header IB Isolation Valve I-FCV-67-82 Cable IV20008 Reference drawings: 45N1750-6, -22, -24; 45N779-13 6.4.10.1 Notify the Unit Operator that the following equipment will be affected during this functional test:

1. 1-FCV-67-82

'/

Cognizant Engineer

/

/Date

/h 6.4.10.2 At valve 1-FCV-67-82, place the declutch

-i l

lever in " MANUAL", and using the handwheel, )

position the valve to approximately its mid-travel pos tion.

M- .' IWJ d Cognizant Engineer Date 0466Qldar t *-

) :

SQN STI-33 Page 26

', . Revision 0

-- 6.0 INSTRUCTIONS (continued) 6.4.10.3 Request the Shift Engineer (SE) to release the hold order and energize the 480V Reactor MOV Board 182-8 compartment 3C breaker.

' ~

Cognizant Engineer

-l$ff/ 7-

' Date 6.4.10.4 At the local control station JB2008, stroke valve 1-FCV-67-82 by depressing 1-HS-67-828 "CLOSE", then "STOP". Visually observe that ,

valve drives in the closed direction.

NOTE: Consult Operations for approximate maximu allowable stroke time, f

Cognizant Engineer I ////

' Date 6.4.10.5 Notify the Unit 0 rat that system may be returned to it es r J "# # -" ration status.

4 M I

[k

/" Unit Operator Date 0fn

' Cognizant E'ngineer I /h Date 6.4.11 Charging Pump Suction From Refueling Water Storage Tank Valve 1-LCV-62-136 Cable IV21008 S

Reference drawings: 45N1750-3, -13, -16; 45N779-12 CAUTIONS: 1. Do not perform this functional (open 1-LCV-62-136) with a charging pump running if maintaining RCS level is critical.

2. Instructions and precautions of SI-166.6 shall be followed.

6.4.11.1 Notify the Unit Operator that this functional -

test is to be performed in conjunction with the requirements of SI-166.6 and shall immediately precede stroke time testing of valve 1-LCV-62-136.

Q" lCognizaiit 0]16~lneer IE/Afk7 9 'Date 04660/dar

' '- ~

SQN STI-33 Page 27

Revision 0

~4 6.0 INSTRUCTIONS (continued) 6.4.11.2 At valve 1-LCV-62-136, place the declutch lever in " MANUAL", and using the handwheel, position the valve to approximately its mid-travel position. .

& 0 dl

' ' Cognizant Tngineer

~

I Yf.27k/?

~Date 6.4.11.3 Request the Shift Engineer (SE) to release I the hold order and energize the 480V Reactor MOV Board 181-B compartment 8C breaker.

I PfMh7 Cognizant Tngineer Date 6.4.11.4 At the local control station JB2066, stroke valve 1-LCV-62-136 by depressing 1-HS-62-136B "CLOSE", then "STOP". Visually observe that valve drives in the closed direction.

Q f0w Cognizant Engineer I W29fff Date 6.4.11.5 Notify the Unit Operator that the system may be returned to desired operating status.

QA fD Cognizant En'gineer WZ9fff Date l 6.4.11.6 Perform SI-166.6 for valve 1-LCV-62-136.

Attach copies'of completed SI data sheets to 1 the Data Package. >

QA f Cognizant Engineer WZ9f77 j Date 6.4.12 Emergency Boration Isolation Valve 1-FCV-62-138B  ;

1 Cable IV29758 .

I Reference drawings: 45N1750-3, -13. -16; 45N779-24 CAUTIONS: 1. BAT pumps shall be locked out before -

performing this functional, (stroking 1-FCV-62-1388), to prevent injecting Boric Acid into RCS.  !

l

2. Instructions and precautions of SI-166.6 shall be followed. I 1

04660/dar

/Cf 27- N S Y SQN STI-33 f f- /0 o $ ~2-I-f Page 28 (i)..

6.0 ..

INSTRUCTIONS (continued)

Revision 0-6.4.12.1 Notify the Unit Operator that this functional test is to be performed in conjunction with the-requirements of SI-166.6 and shall immediately precede stroke time testing of ' j valve 1-FCV-62-1388. i Y dkk

'~ ~ Cognl7sn't Engineer 18h9k T "Dat6 6.4.12.2 At valve 1-FCV-62-1388, place the declutch l j

lever in " MANUAL", and using the handwheel, position the valve to approximately its mid-travel position.

Q'~A Y f 0 s/d Cognizatrt'E6gineer I W231b1 Date '

6.4.12.3 Request the Shift Engineer (SE) to release the hold order and energize the 480V Reactor MOV Board 181-B compartment 8E breaker.

i & C ognizant Edgineerf0 Date nA U IEb9b7 6.4.12.4 At the local control station JB1446, stroke valve 1-FCV-62-1388 by depressing 1-HS-62-138B "CLOSE", then "STOP" Visually-observe directio that valve dr v s in the-closed. f

,/f >AJ/ f[,2 9/ V7 6.4.12.5 4y~ u Mg ku- ow-Notify the Unit Operator that the system may be returned to desired operating status. '

0A$0d~

Cogni zan t'Eilgineer

~ l P/29lP7 '

Date 6.4.12.6 Perform SI-166.6 for valve 1-FCV-62-1388.

Attach copies of completed SI data sheets to the Data Package.

0' ACognfi zan t 'Eng&_- ineer IPbffr7 Date 04660/dar ,

y -

- ~ ---

. . fcf 2 7 - N W Sqn p a y_ ' ll k'T-STI-33 Page(/)Ch 6.0- Revision 0

' INSTRUCTION!S '(continued)-

4..

6, 4. 13

-_ . e gaq,,,, p Cable: /v't w o 4. .

Reference drawings: vr/>v79-t'3, 4/re.// 7 to - 3, fg 6 . 4 .13. 1 Notify the Unit Operator that the following equipment will be affected during this functional test:

1. /- F C V ~ S T ' '7 7 .

jYfd> $1 W,29hl Cognizant E'ngineer Date' 6.4./3.2 A t va l ve /- rev e t -17 place the declutch-lever in " MANUAL", and using the handwheel, position theposition.

mid-travel valve to approximately its f0dA Eb9lr7 Cognizant Enfineer Date

6. 4.13. 3 Request the Shift Engineer (SE) to release the hold order and energize the 480V Reactor MOV Board / B/-4 compartment 9M breaker.

' f&eYI 8/.Mf 77' Cognizant Engineer Date

6. 4./3. 4 At the local control station JB/r??, stroke .*

valve /-/<v AP7 by depressing / Ns t: ?M "CLOSE", then "STOP". Visually observe that VALVE NOTE: Fuu YforCLO.

Consult Operations approximate SED cN4'(6Ix16 -

If E.lT maximum allowable stroke' time. pongjj

&)f0M

~ "

Cognizant Engineer I8/bf/h7 Date OMASN' 6.4.0.5 Notify the Unit Operator that system may be returned to its desired configuration status.

h' i Unft Operator I

7C k f i

Da't e / ~

["Lff0nfa,$I f/27hf Co'g n izaY Ngiocer Data

ZC= 27 - /YCV SQi1 STI-33 77c #v _ /2. o [ t /

dP F' fcp C7- /'dY Page 29 Revision 0 6.0 INSTRUCTIONS (continued) f y _:

f

6. 4.1Y Equipment can be returned to service. Sign off on pages 11 through 13 of the Data Package.

6.5 Test Comuletion 6.5.1 Restore the test area to a pretest condition per SQA66.

/

._ Cognizant Engineer Date 6.5.2 Notify the ' Shift Engir.eer (SE) of the completion of this' test.

/ /

Shift Engineer Date Time 6.5.3 Notify Maintenance and Surveillance Scheduling Section of the completion of this test.

/

MSS Date 7.0 ACCEPTANCE CRITERIA 7.1 The cables must pass the in-conduit DC high voltage test. A j . ,, y h cablepassesifeachconductorinthatcablep)ses. A conductor passes if and only if the current reading taken at the end of the first minute ("I min.") is greater than or equal to the current reading taken at the end of the fifth minute ("5 min.")

7.2 If any cable failures occur, enter on the test Deficiency Log, page 15 of the Data Package and comply with the instructions therein and notify DNE-EEB. >

{

04660/dar }

i 1

'1 I

l I 5 ' .,j l

SON STI-33 Page 30 Revision 0 DATA PACKAGE Test Data Sheet

_ , Page 1 of 19

, Conduit MCl4938 EQUIPMENT ISOLATION LIST

. Question A Question B Removal from Service Out of Service Approved. Configuration Verified Equipment Identification Log Engry Made., and Re-Yes Hold dundant Train in Service Steo 6.1.1 -

Yes/No No Order shift Enar. / Date Coanizant Enor/Date CCS Pumps 2A-A to 2B-B -

Suction Isolation Valve <

0-FCV-70-39 fed from 480V ,

Reactor MOV Boart 2B2-B Compartment 11C Circuit d/ -

Breaker to isolate -- I /

Cable 2V32208. M/

IED V

1 1913 ~

.t

[Ju,

.n 5-n -M

  1. ' I" ~ .

l CCS Pumps 2A-A and 2B-B to C-S Pump Inlet Isolation Valve 2-FCV-70-78 fed df from 480V Reactor MOV Board 282-8 Compartment 10E Circuit Breaker to isolate g,)3-T7 O Y fr/2- bbi' 9-73 -k?

r CCS Pumps 2A-A and 28-B to C-S Pump Inlet Isolation Valve 2-FCV-70-76 fed from l

480V Reactor MOV Board 2B2-B Compartment 14A g d) ,

N Circuit Breaker to isolate D Y c, Y g g$ y. f,,,2, Ge>3 M ERCW Meader IB Isolation Valve 1-FCV-3-126A f or IB-B MDAF Pump fed from 480V g';

Reactor MOV Board 182-B .

Compartment 2C Circuit Breaker to isolate Cable IV29408. 4j s7 g~v1 o .)1, f No } 56L . 3.% b,-J '1 *1 ,

Reactor Coolant Pump 011 Cooler Return Containment Isolation Valve r 1-FCV-70-140 fed from 480V Rec; tor MOV Board 1B2-B Comportment 15C Circuit h, Breaker to isolate Cable Cable lv28888. .

oO ,. $ 3 #

g / i Tf 2 - . ,_. [. .____ $ o 3 y/

l ERCW Header 1B Isolation <

l Valve 1-FCV-3-1268 for IB.B MDAF Pumn fed from A

g.

j f.

480V Reactor MOV Board 1B2-0 Compartment 2B C7 -

Circiut Breaker to isolate eg.p3-oe O

No ) S b2 $agg Juestions:

A. Does removal of this equipmer t from service require entering into a limited cor1dition for operation (LCO) action time?

B. Configuration s eg entry made on equipment removed f rom service?

0472Q/dar

+ - 1

5I-33 ~6 OATA PACKAGE ~

Test Data Sheet Page 31 Revision 0 jd9 /3 o ./* '

Page 2 of 19 Conduit MC14938-EQUIPMENT ISOLATION LIST Question A Question D Removal from Service Out of Service Equipment Identification Approsed. Configuration tog Engry Made, and Re- Verified Yes Hold _dondant Train in Service Yes/No No lOrde r Shift Enne. / Date Sten 6.1.1 CCS Pumps 1A-A to IB-B teen, rant Enne/Date Suction Isolation Valve 0-FCV-70-34 fed from 480V g Reactor MOV Board 182-8 Compartment 11C Circuit '

Breaker to isolate Cable IV32208. .i No IT/2- g =1 -

~

h ' ((

CCS Pumps IA-A and IB-B to h-tr C-5 Pump Inle.t Isolation -

Valve 1-FCV'70-64 fed from p

480V Reactor HOV Board ,

6' .

1B2-8 Compartment 10E Circuit Breaker to isolate Cable IV25448 o ,,4 j .

WA _

l I 5~1>  % *> > -k'1 CCS Pumps IA-A and IB-B to C-S Pump Inlet Isolation Valve I-FCV-70-74 fed from _

(

480V Reactor HOV Board 182-B Compartment 14A -

Circuit Breaker to isolate ' y~o 7

' O/

ko f l 511.- N W,$_ G< n &s j

Aux Bldg ERCW Supply Header

! IB Isolation Valve 1-FCV-67-82 fed from 480V g Reactor Board 182.B '

Compartment,3C Circuit Breaker to isolate -

Cable IV20008. ,j y

g

[,gf7 r b-

/

f Charging Pump Suction from Refueling Water Storage Tank Valve 1-LCV-62-136 r-fed from 480V Reactor MOV Soard 181-B Compartment 8C '

Circuit Drekaer to isolate .,

C" 'v2iOOB.

jg y $L }-

Emergency Boration m- bEA s->>.-n Isolation Valve 1-FCV-62-1388 fed from 480V Reactor NOV Board 1BI-B r Compartment BE Circuit a V 7 Y g c%:., n m n-

~~~

]

Wi+<. /fC.tf

  • C 'L *1?

{#,/ fe... yaw Aros.4<- ,

/7N &me,/ /d / - Q Co-ft-Gd Cov e r/ L esl*r f

, ,a .- . aa.

g. 73 -7 ?

[ _ / t/ 7.*2 Y o 6, MO l51 & b b-a k 5 >3*97 estions:

A.

operation (L(0) action timefDoes removal of this equipment from service require entering .

a limited condition for 8

Configuration tog entry made on equipment removed from service?

t  ?

SQN STI-33 q 3 Page 32

(/, j Revision 0 DATA PACKAGE

_ Test Data Sheet Page 3 of 19 CONDUIT MCl4938 Cable Disconnect List

. ITEM NO.

1. g [ Cable 2V32208, T1, T2 and T3 conductors at
1. 480V Rx MOV Bd 2B2-B, Compartment ilC (dwg 45N2750-9) ,
2. 0-FCV-70-39 (dwg 45N2750-23) ' -
2. Dtl Cable 2V2544B, T1, T2 and T3 conductors at
1. 480V Rx MOV Bd 2B2-B, Compartment 10E (dwg 45N2750-9) pr-(- 2. 2-FCV-70-78 (spliced) (dwg 45N2750-23)
3. Cable 2V25508, T1, T2 and T3 conductors at
1. 480V Rx MOV Bd 282-B, Compartment 14A (dwg 45N2750-10)
2. 2-FCV-70-76 (dwg 45N2750-23) 7
4. Cable IV29408, T1, T2 and T3 conductors at
1. 480V Rx MOV Bd 182-B, Compartment 2C (dwg 45N1750-6)e f
2. 1-FCV-3-126A (dwg 45N1750-21) -

341 5. Cable IV2888B, T1, T2 and T3 conductors at

1. 480V Rx MOV Bd 182-B, Compartment 15C (dwg 45N1750-10)s
2. 1-FCV-70-140 (dwg 45N1750-21)

S

6. Cable IV29608, T1, T2 and T3 conductors at
1. 480V Rx MOV Bd 1B2-B, Compartment 2B (dwg 45N1750-6) s
2. 1-FCV-3-126B (dwg 45N1750-21) f g
7. Cable 1V32208, T1, T2 and T3 conductors at
1. 480V Rx MOV Bd 182-B, Compartment llc (dwg 45N1750-9)
2. 0-FCV-70-34 (dwg 45N1750-23 V. -

WDCognizant Engineer s I 8/23/ky -

Date 04730/lds

\

O

1 ZC f 87- /v 2'?

s'<1[te 14 o f ~2- I Soft (1j STI-33 Page 33 Revision 0 DATA PACKAGE Test Data Sheet Page 4 of 19 CONDUIT MC14938 ITEM NO. Cable Disconnect List

+

8. D N,-

Cable IV2544B, T1,,T2 and T3 conductors at 1.

2. 480V Rx MOV Bd 182-B, Compartment 10E (dwg 45N1750-9) 1-FCV-70-64 (spliced)

(dwg 45N1750-23) V 9.

Cable IV25508 T1, T2 and T3 conductors at 1.

04'-f 480V Rx MOV Bd 182-B, Compartment 14A (dwg 45N1750-10)

2. 1-FCV-70-74 (dwg 45N1750-23) '

10.

Cable IV20008, T1, T2 and T3 conductors at 1.

480V Rx MOV Bd IB2-B, Compartment 3C n! 2. 1-FCV-67-82 (spliced) (dwg 45N1750-6) g t

' (dwg 45N1750-22) 11.

Cable IV21008, T1, T2 and T3 conductors at ,

1.

480V Rx MOV Bd IBI-B, Compartment 8C l

2. 1-LCV-62-136 (dwg 45N1750-3) /

(dug 45N1750-13) -

)

12. {

Cable IV2975B, T1, T2 and T3 conductors at 1.

480V Rx MOV Bd 181-8, Compartment 8E

2. 1-FCV-62-138B (dwg 45N1750-3) # '

(dwg 45N1750-13) -

73 G 4/e / V 2 2'fo2, ri, 7z, ,, / 73 e ,,J.n/as a/ i

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Page 45 Revision 0 i DATA PACKAGE TEST DATA SHEET Page 16 of 19 l I.

Conduit & Cable Data Condui t Number MCl4938 Conduit Size and Material 4A -

l CABLE NO. MARK No. INSUL. THICKNESS TYPE INSULATION TYPE (INCHES)

1. 2V32208 WLC 3cl2
2. CPJJ 0.030 2V2'5448 WLC 3cl2
3. CPJJ 0.030 2V25508 WLC 3cl2 .

4 CPJJ 0.030 IV29408 WLC 3cl2 CPJJ 0.030

5. IV28888 WLC 3cl2
6. CPJJ 0.030 l IV29608 WLC 3cl2 CPJJ 0.030
7. IV32208 WLC 3cl2 CPJJ 0.030
8. IV2544B WLC 3cl2 CPJJ 0.030
9. IV25508 WLC 3cl2 CPJJ 0.030
10. IV20008 WLC 3cl2 CPJJ
11. IV2100B 0.030 WLC 3cl2 CPJJ 0.030
12. IV2975B WLC 3cl2 CPJJ 0.030 13, /Vnvos ulc 3 c/ t- 07J a- @

04750/1ds

i SQN STI-33 i Page 46 (

Revision 0 DATA PACKAGE Test Data Package

. Page 17 of 19 II. Cable Routing Data Connection Diagram Cable No. 2V32208 From: 480V Reactor MOV Bd 2B2-B, Cmprmt 11C, RAll/749 45N2750-9 To: 0-FCV-70-39, TA2/690 45N2750-23 Conduit Routing: 2PL67318, MC1493B, IV2588B Tray Routing: HG-B, HH-8, HI-8, HL-B For: Power Supply to CCS Pump 2A-A to 28-8 Suct Isol Valve 0-FCV-70-39 Cable No. 2V2544B From: 480V Reactor MOV Bd 282-B, Cmprmt 10E, RAl2/749 45N2750-9 To: 2-FCV-70-78, TA2/690 45N2750-23 Conduit Routing: 2PL67268, MCl493B, IV25888 Tray routing: HG-B, HP-8, HI-8, HL-B For: Power Supply to CCS Pumps 2A-A & 28-B to C-S Pump Inlet Isol Valve 2-FCV-70-78 Cable No. 2V2550B From: 480V Reactor MOV Bd 2B2-B, Cmprmt 10A, RAll/749 45N2750-10 To: 2-FCV-70-76, TA2/690 45N2750-23 Conduit Routing: 2PL67468, MC1493B, IV2588B, 1V2587B Tray Routing: HG-B, HH-8, HI-B, HL-B For: Power Supply to CCS Pumps 2A-A & 2B-B to C-S Pump Inlet Isol Valve 2-FCV-70-76 Cable No, IV29408

  • From: 480V Reactor MOV Bd 182-B, Cmprmt 2C, SA4/749 45N1750-6 To: 1-FCV-3-126A, SA4/690 45N1750-21 Conduit Routing: IPL66868, MC1493B, MC15318, 1V2946B Tray Routing: HL-B, FI-B For: Power Supply to ERCH Hdr 1B Isol Valve 1-FCV-3-126A for 18-B MDAF Pump Cable No. IV2888B From: 480V Reactor MOV Bd IB2-B, Cmprmt 15C, RA4/749 45N1750-10 -

To: 1-FCV-70-140, WA4/690 45N1750-21 Conduit Routing: MC15078, MC15158, IV2199B, IV21986, IPL6751B, MCl4938, MC1531B Tray Routing: FI-8, FN-8, HM-8, HL-B For: Power Supply to Reactor Coolant Pump 011 Cooler Return Containment Isolation Valve 1-FCV-70-140 04750/lds l

l L

SON STI-33 Page 47 DATA PACKAGE

~--

Test Data Package Page 18 of 19 II. Cable Routing Data Connection Diagram Cable No. IV2960B From: 480V Reactor MOV Bd IB2-B, Cmprmt 2B, SA4/749 45N1750-6 To: 1-FCV-3-126B, SA4/690 45N1750-21 Conduit Routing: 1PL66868, MC14938, MC15318, IV2946B Tray Routing: HL-B, FI-B For: Power Supply to ERCH Hdr 1B Isol Valve 1-FCV-3-1268 for IB-B MDAF Pump I

Cable No. IV3220B From: 480V Reactor MOV Bd 182-B, Cmprmt 11C, RA4/749 45N1750-9 To: 0-FCV-70-34, TA2/690 45N1750-23 Conduit Routing: MC14938, IV25868, IV25888, IV2595B, IPL67318 Tray Routing: HM-B, HL-B For: Power Supply to CCS Pump 1A-A to 18-8 Suct Isol Valve 0-FCV-70-34 Cable No. IV25448 From: 480V Reactor MOV Bd 1B2-B, Cmprmt 10E, RA4/749 45N1750-9 To: 1-FCV-70-64, TA2/690 45N1750-23 Conduit Routing: MC1493B, IV25888, IV25878, IV25868, IV25958 Tray Routing: HM-B, HL-B For: Power Supply to CCS Pumps 1A-A & 18-B to C-S Pump Inlet Isol Valve 1-FCV-70-64 5

Cable No. IV25508 From: 480V Reactor MOV Bd IB2-B, Cmprmt 14A, RA4/749 45N1750-10 To: 1-FCV-70-74, TA2/690 45N1750-23 Conduit Routing: MCl4936, IV2588B, IV25878, IV2586B, IPL6746B Tray Routing: HM-8, HL-B For: Power Supply to CCS Pumps lA-A & IB-B to C-5 Pump Inlet Isol Valve 1-FCV-70-74 Cable No. IV2000B -

From: 480V Reactor MOV Bd 182-0, Cmprmt 3C, RA4/749 45N1750-6 To: 1-FCV-67-82, UA1/669 45N1750-22 Conduit Routing: IPL66918, MCl4938, IV2009B Tray Routing: HM-B, HL-B For: Power Supply to Aux Bldg ERCW Supply Hdr IB Isol Valve 1-FCV-67-82 04750/lds

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SON Ed' f 27- Pf 9 5/

STI-33 F" v " # [ 1/

Page 48 Revision 0 DATA PACKAGE

~

Test Data Package Page 19 of 19 i 1

II. Cable Routing Data Connection Cable No.

Diaaram ,j IV2100B  ;

From: l 480V Reactor MOV Bd IB1-B, Cmprmt 8C, RA4/749 To: 1-LCV-62-136 UA3/669 45N1750-3 i Con.duit Routing: IPL6516B, MC1493B, TV2009B 45N1750-13  !

Tr'ay Routing: HK-8, HL-B For: ,

Power Supply to Charging Pump Suction From Refueling Water Storage Tk Valve 1-LCV-62-136 i Cable No. IV29758 {,

From: i 480V Reactor MOV Bd IB1-B, Cmprmt 8E, SA4/749 To: 1-FCV-62-1388, VA4/690 45N1750-3 l Conduit Routing: IPL3192B, IPL31288, IV21808, IV2181B, 45N1750-13 j IPL1516B MC14938, MC1531B Tray Routing: HK-8, HL-B, FI-B For: Power Supply to Emergency Boration Isolation Valve 1-FCV-62-138B {

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SON i STI-33 $

Page 49 Revision 0 -) l

(

ATTACHMENT 1 l Page 1 of 2

' l j STI-33 TRAINING ROSTER l i Subject of Training: IMPLEMENTATION OF STI-33 i

Date of Training: 6 -LS - O This training consisted of formal instruction on the following:

- Objectives .

- References  !

- Prerequisites

- Precautions and Limitations

- Special Test Equipment

- Instructions

- Acceptance Criteria l - USQD

- Test Director's Responsibility l Test Director's Name: Mb lNc. bd?#d Test Director's Signature: u '[

Date N / 8 -2f- G7 SIGNATURES BELON INDICATE THAT INDIVIDUALS UNDERSTOOD THE SUBJECT. ,

SSN res-to-m?

Print tJame Arr?. //OACM M&A.

Signature [ $./ Grade M0 0 -ine &w fu.n wc 22 - W 4rsn/ai Ox/$(

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STI-33 TRAINING ROSTER Subject of Training: IMPLEMENTATION OF STI-33 Date of Training: h/23 /27 This training consisted of formal instruction on the following:

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SQN STI-33 Page 49  !

Revision 0 ATTACHMENT 1 Page 1 of 2 STI-33 TRAINING ROSTER Subject of Training: IMPLEMENTATION OF STI-33 Date of Training:

This training consisted of formal instruction on the following:

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SQN STI-33 Page 49 Revision 0 N ATTACHMENT 1 Page 1 of 2

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SQii STI-33 Page 49 Revision 0 ATTACHMENT 1 Page 1 of 2 STI-33 TRAINING ROSTER Subject of Training: IMPLEMENTATION OF STI-33 Date of Training:

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ATTACHMENT 1 Page 1 of 2 STI-33 TRAINING ROSTER Subject of Training: IMPLEMENTATION OF STI-33 Date of Training:

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This training consisted of formal instruction on the following:

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- Test Director's Responsibility Test Director's Name:

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SSN Print Name Sicnature Dept./ Grade l

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SQN STI-33 Page 49 Revision 0 i

ATTACHMENT 1 Page 1 of 2 STI-33 TRAINING ROSTER Subject of Training: IMPLEMENTATION OF STI-33 Date of Training:

This training consisted of formal instruction on the following:

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SON STI-33 Page 49 Revision 0 ATTACHMENT 1 Page 1 of 2 STI-33 TRAINING ROSTER Subject of Training: IMPLEMENTATION OF STI-33 Date of Training:

This training consisted of formal instruction on the following:

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- Test Director's Responsibility Test Director's Name:

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ATTACHMENT 1 Page 1 of 2 STI-33 TRAINING ROSTER Subject of Training: IMPLEMENTATION OF STI-33 Date of Training:

This training consisted of formal instruction on the following:

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SQi1 STI-33 Page 51 Revision 0 Attachment 2 Page 1 of 2 LIST OF EQUIPMENT AFFECTED DURING DC HIGH VOLTAGE TEST OF CABLES_

CABLE NO. SCHEMATIC NO. DESCRIPTION

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2V3220B 45N779-40 Component cooling system pump 2A-A to 28-8 suction isolation valve 0-FCV-70-39 2V2544B 45N779-13 Component cooling system pumps 2A-A & 28-B to C-S Pump inlet isolation valve 2-FCV-70-78 2V2550B 45N779-13 Component cooling system pumps 2A-A & 2B-B to C-5 Pump inlet isolation valve 2-FCV-70-76 IV29408 45N779-23 Essential raw cooling water system header 1B isolation valve 1-FCV-3-126A for IB-B MDAF Pump 45N765-6 Motor Driven Aux Feedwater (MDAF) Pump 1B-8 IV2888B 45N779-35 Reactor coolant pump oil cooler return containment isolation valve 1-FCV-70-140 IV29608 45N779-23 Essential raw cooling water system header 1B isolation valve 1-FCV-3-126B for IB-B MDAF Pump 45N765-6 Motor Driven Aux Feedwater (MDAF) Pump 18-B IV32208 45N779-40 Component cooling system pump 1A-A to IB-B suction isolation valve 0-FCV-70-34 IV25448 45N779-13 Component cooling system pump 1A-A & IB-B to C-S Pump inlet isolation valve 1-FCV-70-64 IV2550B 45N779-13 Component cooling system pump 1A-A & 18-B to C-S Pump inlet isolation valve 1-FCV-70-74 IV20008 4SN779-13 Aux bldg essential raw cooling water supply -

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... Attachment 2 Page 2 of 2 LIST OF EQUIPMENT AFFECTED DURING DC HIGH VOLTAG

_ CABLE NO. SCHEMATIC NO. .

DESCRIPTIOil IV2100B 45N779-12 Charging pump suction from refueling water storage tank valve 1-LCV-62-136

,.. 45N657-4 Separation Relays ll2EX & 112EXA 45N779-11 Volume Control Tank Outlet Isolation Valve 1-LCV-62-132 IV2975B 45N779-24 Emergency boration isolation valve 1-FCV-62-138B

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ATTACHMENT 3 Page 1 of 2 STI-33 TRAINING ROSTER Subject of Training: PRE-FUNCTIONAL TEST BRIEFING: FUNCTIONALTESTN0.4.Y.3 .

Date of Training: 8-2.9-97 This training consisted of formal instruction on the following:

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STI-33 TRAINING ROSTER Subject of Training: PRE-FUNCTIONAL TEST BRIEFING: FUNCTIONAL TEST NO. b , Y 3 Date of Training: 2 /87 This training consisted of formal instruction on the following:

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Date of Training: [///I/

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SON STI-33 Page 53 Revision 0 ATTACHMENT 3 Page 1 of 2 STI-33 TRAINING ROSTER Subject of Training: PRE-FUNCTIONAL TEST BRIEFING: FUNCTIONAL TEST NO.

Date of Training:

This training consisted of formal instruction on the following:

- Objectives

- References

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- Special Test Equipment

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- Test Director's Responsibility Test Director's Name:

Test Director's Signature: /

Date SIGNATURES BELOW INDICATE THAT INDIVIDUALS UNDERSTOOD THE SUBJECT.

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STI-33 Page 53 Revision 0 ATTACHMENT 3 Page 1 of 2 STI-33 TRAINING ROSTER i

Subject of Training: PRE-FUNCTIONAL TEST BRIEFING: FUNCTIONAL TEST NO. ,

Date of Training:

This training consisted of formal instruction on the following:

- Objectives

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- Test Director's Responsibility Test Director's Name:

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STI-33 Page 53 Revision 0 ATTACHMENT 3 Page 1 of 2 STI-33 TRAINING ROSTER Subject of Training: PRE-FUNCTIONAL TEST BRIEFING: FUNCTIONAL TEST NO. l Date of Training: I

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Date SIGNATURES BELOW INDICATE THAT INDIVIDUALS UNDERSTOOD THE SUBJECT.

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' ATTACHMENT 3 Page 1 of 2 STI-33 TRAINING ROSTER Subject of Training: PRE-FUNCTIONAL TEST BRIEFING: FUNCTIONAL TEST NO. _ _

Date of Training:

This training consisted of formal instruction on the following:

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- Test Director's Responsibility Test Director's Name: '

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Date SIGNATURES BELOW INDICATE THAT INDIVIDUALS UNDERST0OD THE SUBJECT.

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SON STI-33 Page 53 Revision 0 ATTACHMENT 3 Page 1 of 2 STI-33 TRAINING ROSTER Subject of Training: PRE-FUNCTIONAL TEST BRIEFING: FUNCTIONAL TEST NO.

Date of Training:

This training consisted of formal instruction on the following:

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- Test Director's Responsibility Test Director's Name:

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Date SIGNATUR'i BELOW INDICATE THAT INDIVIDUALS UNDERSTOOD THE SUBJECT.

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SON STI-33 Page 53 Revision 0 ATTACHMENT 3 Page 1 of 2 STI-33 TRAINING ROSTER Subject of Training: PRE-FUNCTIONAL TEST BRIEFING: FUNCTIONAL TEST NO.

Date of Training:

This training consisted of formal instruction on the following:

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- Test Director's Responsibliity Test Director's Name:

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Date SIGNATURES BELOW INDICATE THAT INDIVIDUALS UNDERSTOOD THE SUBJECT SSN Print Name Slanature Dept./ Grade 04750/lds

SON STI-33 Page 53 Revision 0 ATTACHMENT 3 Page 1 of 2 STI-33 TRAINING ROSTER i

Subject of Training: PRE-FUNCTIONAL TEST BRIEFING: FUNCTIONAL TEST NO. .

Date of Training:

This training consisted of formal instruction on the following:

- Objectives

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- Test Director's Responsiblitty Test Director's Name:

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Page 53 Revision 0 ATTACHMENT 3 Page 1 of 2 STI-33 TRAINING ROSTER Subject of Training: PRE-FUNCTIONAL TEST BRIEFING: FUNCTIONAL TEST NO.

Date of Training:

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Date of Training:

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Date SIGNATURES BELOW INDICATE THAT INDIVIDUALS UNDERSTOOD THE SUBJECT.

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SQN STI-33 Page 53 Revision 0 ATTACHMENT 3 Page 1 of 2 STI-33 TRAINING ROSTER Subject of Training: . PRE-FUNCTIONAL TEST BRIEFING: FUNCTIONAL TEST NO.

Date of Training

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Date of Training:

This training consisted of formal instruction on the following:

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- Test Director's Responsibility Test Director's Name:

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- Test Director's Responsibility Test Director's Name:

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Date SIGNATURES BELOW INDICATE THAT INDIVIDUALS UNDERSTOOD THE SUBJECT.

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SQN STI-33 Page 54 Revision 0 ATTACHMENT 3 Page 2 of 2 STI-33 TRAINING ROSTER PREFUNCTIONAL TEST BRIEFING: FUNCTIONAL TEST NO.

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